WorldWideScience

Sample records for safety meeting summary

  1. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  2. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  3. Transactions of the nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1991-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately

  4. 77 FR 3326 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-01-23

    .... 3] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of Northeast Corridor Safety Committee Meeting. SUMMARY: FRA announced the first meeting of the Northeast Corridor Safety Committee, a Federal...

  5. 76 FR 32391 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2011-06-06

    .... 1] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety Committee Meeting. SUMMARY: FRA announces the first meeting of the Northeast Corridor Safety Committee, a...

  6. Transactions of the twenty-fifth water reactor safety information meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  7. Transactions of the twenty-fifth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session

  8. 76 FR 32390 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2011-06-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee (MCSAC) Meeting. SUMMARY...

  9. 75 FR 2923 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  10. 75 FR 29384 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-05-25

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee meeting. SUMMARY: FMCSA...

  11. 75 FR 72863 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-11-26

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration, DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA announces...

  12. 75 FR 50797 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-08-17

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  13. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  14. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  15. Transactions of the twenty-second water reactor safety information meeting

    International Nuclear Information System (INIS)

    1994-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 22nd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 24--26, 1994. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session. Individual papers have been cataloged separately

  16. 77 FR 62248 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2012-10-12

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2012-0936] Commercial Fishing Safety.... SUMMARY: The Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Washington, DC to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the...

  17. 78 FR 44958 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2013-07-25

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2013-0625] Commercial Fishing Safety.... SUMMARY: The Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Washington, DC to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the...

  18. Transactions of the Twentieth Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

  19. 75 FR 2890 - OSHA Listens: Occupational Safety and Health Administration Stakeholder Meeting

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0004] OSHA Listens: Occupational Safety and Health Administration Stakeholder Meeting AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of public meeting. SUMMARY: The Occupational Safety...

  20. 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

  1. 76 FR 2916 - Houston/Galveston Navigation Safety Advisory Committee; Meetings

    Science.gov (United States)

    2011-01-18

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [USCG-2010-1116] Houston/Galveston Navigation Safety Advisory Committee; Meetings AGENCY: Coast Guard, DHS. ACTION: Notice of Meetings. SUMMARY: The Houston... will meet in Texas City, Texas and Houston, Texas to discuss waterway improvements, aids to navigation...

  2. Topics raised by the summary report of the first review meeting

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 7 of the document contains topics raised by the summary report of the first review meeting. The chapter covers status and position of the regulatory body, collective doses, effluents release trends, adoption of the ICRP 60 and basic safety standards, regulatory strategy, quality assurance, monitoring safety management, international cooperation, probabilistic safety assessment and safety improvement programmes

  3. 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

  4. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

  5. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    International Nuclear Information System (INIS)

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy's efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees' requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees' post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant's requests, a fourth information exchange will be held later in 1997

  6. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part III

    International Nuclear Information System (INIS)

    1976-01-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs

  7. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-01-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs.

  8. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-08-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs.

  9. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part I

    International Nuclear Information System (INIS)

    1975-08-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs

  10. Safety culture in nuclear installations: Summary of an international topical meeting

    International Nuclear Information System (INIS)

    Carnino, A.; Derrough, M.; Weimann, G.

    1996-01-01

    An international topical meeting, Safety Culture in Nuclear Installations, was organized by the American Nuclear Society (ANS) Austria Local Section, cosponsored by the ANS Nuclear Reactor Safety and Human Factors Divisions in cooperation with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD) and held in Vienna April 24-28, 1995. Some 250 experts from 30 different countries and organizations took part in the 85 paper presentations and two workshops. The concept of safety culture was initially used in the first International Nuclear Safety Advisory Group (INSAG) report on the Chernobyl accident analysis report in 1986. Although some elements of safety culture have been used over the years in nuclear safety activities, the new phrase safety culture and the concept were found interesting as highlighting the 'soft' aspects of safety and as encompassing more than human errors. Unfortunately, for many years it was used more in the way of identifying lack of safety culture. Conscious of this application, INSAG further developed the safety culture concept in the INSAG 4 report: The report contains a definition, the universal aspects of safety culture, the two main components of safety culture management and individual behaviour, and performance indicators of a good safety culture. This report is now quite famous and adopted with some additions or complementary definitions by many institutes and organizations for their daily activities

  11. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  12. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  13. 75 FR 57103 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-17

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of... Future of Aviation Advisory Committee (FAAC): Aviation Safety Subcommittee; Notice of Meeting. SUMMARY... of the FAAC Aviation Safety Subcommittee, which will be held September 28, 2010, via teleconference...

  14. 75 FR 60163 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-09-29

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of... Future of Aviation Advisory Committee (FAAC): Aviation Safety Subcommittee; Notice of Meeting. SUMMARY... of the FAAC Aviation Safety Subcommittee, which will be held October 19, 2010, in Everett, Washington...

  15. 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

  16. 78 FR 78362 - National Institute for Occupational Safety and Health Personal; Notice of public meeting in...

    Science.gov (United States)

    2013-12-26

    ... Institute for Occupational Safety and Health Personal; Notice of public meeting in Endicott, New York AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease Control.... SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease...

  17. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key topic / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Traichel, Anke [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany). Dept. of Safety Engineering and Assessment / Proposals Engineering

    2017-04-15

    Summary report on the Key Topic ''Enhanced Safety and Operation Excellence'' Technical Session ''Safety, IT, Hazards and PSA'' of the 47th Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016.

  18. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

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

  19. Summary of the 1982 small tokamak users meeting

    International Nuclear Information System (INIS)

    Sprott, J.C.

    1982-11-01

    On November 1, 1982, the sixth in a series of approximately annual meetings of the users of small tokamaks was held in conjunction with the APS Division of Plasma Physics meeting at New Orleans. The meeting lasted three hours, with 34 people attending. The interest was on strengthening the ties between the small tokamaks and the large tokamaks. Accordingly, the latest meeting was dedicated to this theme, and in contrast to previous meetings, a few representatives from the large tokamaks were invited to attend and make presentations. Summaries of the various talks are included

  20. OECD/CSNI specialist meeting on nuclear aerosols in reactor safety - Summary and Conclusions

    International Nuclear Information System (INIS)

    Allelein, Hans-Josef; Boulaud, Denis; Guentay, Salih; Dehbi, Abdelouahab; Hontanon, Esther; Jokiniemi, Jorma; Jones, Alan V.; Koroll, Grant W.; Tinkler, Charles G.; Schaperow, J.; Royen, Jacques

    1999-01-01

    The Third OECD Specialist Meeting on Nuclear Aerosols in Reactor Safety was organised in Cologne, Germany, from 15-18 June 1998, in collaboration with the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. It was attended by sixty-five specialists representing thirteen OECD Member countries and the Commission of the European Communities. Thirty-nine papers were presented, in eight sessions. The meeting was concluded by a general discussion devoted to the following topics: - What has been solved up to the level of plant applications and accident management? - Where is more work needed for plant applications? Over the last eight years significant progress has been made in source term modelling and code development. Results have been consolidated in codes which are being used for plant calculations to address safety issues. For example, two countries used their source term codes last year to assess the impact of heating from deposited fission products on the potential for steam generator tube rupture. Also, another source term code was used to assess the need of sprays for fission product removal in the proposed design of a new type of reactor. Over the next few years, experiments and model development will continue, with more emphasis on application to risk-important severe accident scenarios

  1. Specialists’ Meeting on Demonstration of Structural Integrity under Normal and Faulted Conditions. Summary Report

    International Nuclear Information System (INIS)

    1981-03-01

    The Specialists' Meeting on ''Demonstration of Structural Integrity under Normal and Faulted Conditions'' was held at Chester, United Kingdom on 3-5 June 1980. The meeting was sponsored by the International Atomic Energy Agency (IAEA) on the recommendation of the International Working Group on Past Reactors (IWGFR). Twenty-one participants from France, the Federal Republic of Germany, Italy, Japan, the Netherlands, the United Kingdom, the United States of America and two international organizations, CEC and IAEA, attended. The purpose of the meeting was to review and discuss methods for assessing the integrity of the LMFBR safety-related structures during normal and abnormal operation, especially in the presence of defects, and to recommend future development. The technical sessions were divided into four topical sessions as follows: 1. National Review Presentations on Demonstration of Structural Integrity; 2. Material Properties; 3. Structural Analysis; 4. Design Approaches and Assessment Experience. During the meeting papers were presented by the participants on behalf of their countries or organizations. Each presentation was followed by an open discussion in the subject covered by the paper and subsequently, session summaries were drafted. After the formal sessions were completed, a final discussion session was held and general conclusions and recommendations were reached by consensus. Session summaries, general conclusions and recommendations, national review papers presented during the first session as well as the agenda of the meeting and the list of participants are given

  2. Meeting of Specialists on the Reliability of Decay Heat Removal Systems for Fast Reactors. Summary Report

    International Nuclear Information System (INIS)

    1975-10-01

    The Specialists Meeting on Reliability of Decay Heat Removal Systems proposed for Fast Reactors was sponsored by the UKAEA Safety & Reliability Directorate and held at Harwell between 28th April and 1st May, 1975. The meeting was attended by delegates from six countries - (USA, Federal Republic of Germany, France, Japan, USSR and the UK). A list of participants is included in an Appendix to this report. The subject matter of the meeting was concerned with the degree to which the ability to maintain decay heat removal from a fast reactor after shutdown in normal and abnormal circumstances could be guaranteed by design provisions and substantiated by reliability analysis techniques, operational testing etc. Consideration of conditions prevailing after a hypothetical core melt down incident were not included in the subject matter. The deliberations of the meeting were focussed at each working session on a defined theme and its dependant topics as shown in the detailed Agenda included in this report. Although provision had been made in the Agenda for a limited amount of discussion of the decay heat rejection problems of Gas Cooled Fast Reactors, delegates had no contributions to offer on this subject. During each session a Recording Secretary prepared a summary of the main points made by national delegates and of the resulting recommendations and conclusions. These draft summaries were made available to delegates during subsequent sessions of the meeting and approved by them for inclusion in the Summary, General Conclusions and Recommendations provided under Table of Contents (item 3 and 4)

  3. Summary view on demonstration reactor safety

    International Nuclear Information System (INIS)

    Satoh, Kazuziro; Kotake, Shoji; Tsukui, Yutaka; Inagaki, Tatsutoshi; Miura, Masanori

    1991-01-01

    This work presents a summary view on safety design approaches for the demonstration fast breeder reactor (DFBR). The safety objective of DFBR is to be at lea as safe as a LWR. Major safety issues discussed in this paper are; reduction of sodium void reactivity worth, adoption of self-actuated mechanism in the backup shutdown system, use of the direct reactor auxiliary cooling system (DRACS), provision of the containment system. (author)

  4. International Working Group on Fast Reactors Thirteenth Annual Meeting. Summary Report. Part II

    International Nuclear Information System (INIS)

    1980-10-01

    The Thirteenth Annual Meeting of the IAEA International Working Group on Fast Reactors was held at the IAEA Headquarters, Vienna, Austria from 9 to 11 April 1980. The Summary Report (Part I) contains the Minutes of the Meeting. The Summary Report (Part II) contains the papers which review the national programme in the field of LMFBRs and other presentations at the Meeting. The Summary Report (Part III) contains the discussions on the review of the national programmes

  5. International Working Group on Fast Reactors Thirteenth Annual Meeting. Summary Report. Part I

    International Nuclear Information System (INIS)

    1980-09-01

    The Thirteenth Annual Meeting of the IAEA International Working Group on Fast Reactors was held at the IAEA Headquarters, Vienna, Austria from 9 to 11 April 1980. The Summary Report (Part I) contains the Minutes of the Meeting. The Summary Report (Part II) contains the papers which review the national programme in the field of LMFBRs and other presentations at the Meeting. The Summary Report (Part III) contains the discussions on the review of the national programmes

  6. International Working Group on Past Reactors Thirteenth Annual Meeting. Summary Report. Part III

    International Nuclear Information System (INIS)

    1981-04-01

    The Thirteenth Annual Meeting of the IAEA International Working Group on Fast Reactors was held at the IAEA Headquarters, Vienna, Austria from 9 to 11 April 1980. The Summary Report (Part I) contains the Minutes of the Meeting. The Summary Report (Part II) contains the papers which review the national programme in the field of LMFBRs and other presentations at the Meeting. The Summary Report (Part III) contains the discussions on the review of the national programmes

  7. Meeting of specialists on 'Operational Safety of Sodium Circuits', Risley, UK, March 17-19, 1971. Summary report

    International Nuclear Information System (INIS)

    1971-01-01

    The meeting was attended by 20 delegates fyom Belgium, France, West Germany, Italy, Japan, the Netherlands, and the United Kingdom. Discussion took place in the following 5 Sessions: Safety Aspects of Design and Construction; Operational Practices; Sodium Leakage Phenomena; Emergency Procedures; Case Histories of Incidents. The formal papers tabled by the delegates at the meeting are reproduced in Appendix 2 of this report. At the final session of the meeting, the delegates agreed on the following report. The case histories of incidents as presented by various delegates are included in Appendix 2 of this report

  8. Report on the environmental safety evaluation sub-committee meetings in fiscal 1987; 1987 nendo kankyo anzensei hyoka bukai hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-03-01

    The environmental safety evaluation sub-committee has held two meeting in the current fiscal year as described below. The first sub-committee meeting (August 25, 1987) was held for the agenda of the summary of future test plans, the result of overseas surveys in fiscal 1986, the results of tests in fiscal 1986, and the summary of the test plan for fiscal 1987. The major agendum of the second sub-committee meeting (February 23) was the interim reports on the overseas survey results and the safety tests in fiscal 1987. NEDO intends to ensure the labor hygiene for workers in coal liquefying plants, the effect of liquefied oil on users' health, and social acceptability of liquefied oil. Therefore, a safety test for liquefied oil in the primary hydrogenation process was performed provisionally on brown coal PP in the initial stage of operation, in addition to bituminous coal liquefied oil at the existing 1-t/d PDU. The main contents of the test performed by NEDO are based on the labor safety and hygiene law and the law related to regulation on the deliberation and manufacture of chemical materials. Different tests using guinea pigs were carried out on the total fraction mixed at the 1-t/d PDU, and each fraction of light and heavy oils, where the liquefied oil was verified to have minor degree of toxicity. (NEDO)

  9. Issues relating to safety standards on the geological disposal of radioactive waste. Proceedings of a specialists meeting

    International Nuclear Information System (INIS)

    2002-06-01

    Within the International Atomic Energy Agency focus is currently being placed on establishing safety standards for the geological disposal of radioactive waste. This is a challenging task and a Specialists Meeting was held from 18 to 22 June 2001 with the intention of providing a mechanism for promoting discussion on some of the associated scientific and technical issues and as a means of developing the consensus needed for establishing the standards. The meeting used, as its basis, a number of position papers developed in recent years with the help of a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, together with selected relevant regional and national papers. The report contains the summaries of the sessions of the Specialists Meeting together with the conclusions drawn relevant to the establishment of standards. The sessions of the Meeting addressed the following topics: Common framework for radioactive waste disposal; Making the safety case - demonstrating compliance; Safety indicators; Reference critical groups and biospheres; Human intrusion; Reversibility and retrievability; Monitoring and institutional control. The publication contains 26 individual presentations delivered by participants. Each of these presentations was indexed separately

  10. Proceedings of fuel safety research specialists' meeting

    International Nuclear Information System (INIS)

    Suzuki, Motoe

    2002-08-01

    Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

  11. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1983-06-01

    The unresolved safety issues summary is designed to provide the management of the nuclear regulatory commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to congress pursuant to section 210 of the Energy Reorganization Act of 1974 as amended. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  12. 76 FR 34139 - Northeast Corridor Safety Committee; Meeting Postponement

    Science.gov (United States)

    2011-06-10

    .... 2] Northeast Corridor Safety Committee; Meeting Postponement AGENCY: Federal Railroad Administration... announced the first meeting of the Northeast Corridor Safety Committee, a Federal Advisory Committee... future date. DATES: The meeting of the Northeast Corridor Safety Committee scheduled to commence on...

  13. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE); Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection

    2016-12-15

    Summary report on the Key Topic 'Enhanced Safety and Operation Excellence' Focus Session 'Radiation Protection' of the 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  14. 76 FR 23339 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-04-26

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-043)] Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of meeting... Register of April 6, 2011, announcing a meeting of the Aerospace Safety Advisory Panel (ASAP) to take place...

  15. 2010 Atmospheric System Research (ASR) Science Team Meeting Summary

    Energy Technology Data Exchange (ETDEWEB)

    Dupont, DL

    2011-05-04

    This document contains the summaries of papers presented in poster format at the March 2010 Atmospheric System Research Science Team Meeting held in Bethesda, Maryland. More than 260 posters were presented during the Science Team Meeting. Posters were sorted into the following subject areas: aerosol-cloud-radiation interactions, aerosol properties, atmospheric state and surface, cloud properties, field campaigns, infrastructure and outreach, instruments, modeling, and radiation. To put these posters in context, the status of ASR at the time of the meeting is provided here.

  16. Summary records of the meetings of INFCE Working Group 6

    International Nuclear Information System (INIS)

    These were 6 meetings of Working Group 6 that took place between 8 December 1977 and 7 September 1979. This document consists of the summaries of those meetings and it reports on the objectives of the Working Group, the participants, the guidelines for the study, and the outline of the final report

  17. Summary records of meetings of INFCE/WG.1 - First to seventh meetings

    International Nuclear Information System (INIS)

    Seven meetings of INFCE/WG.1 were held in the period of 26 January 1978 to 14 September 1979. The activities of Working Group 1 during this period are presented in 7 Summary Records. The main activity areas are: revision of uranium, heavy water and thorium availability; consideration of special needs of developing countries

  18. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Focus session: International operational experience

    Energy Technology Data Exchange (ETDEWEB)

    Mohrbach, Ludger [VGB PowerTech e.V., Essen (Germany). Abteilung ' ' N' ' ; Gottschling, Helge

    2017-11-15

    Summary report on the Key Topic Enhanced Safety and Operation Excellence: Focus Session: International Operational Experience and the Nuclear Energy Campus of the 48{sup th} Annual Meeting on Nuclear Technology (AMNT 2017) held in Berlin, 16 to 17 May 2017.

  19. 76 FR 24504 - National Offshore Safety Advisory Committee

    Science.gov (United States)

    2011-05-02

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. USCG-2011-0183] National Offshore Safety Advisory... Committee Meeting. SUMMARY: The National Offshore Safety Advisory Committee (NOSAC) will meet on May 19... completed its business. ADDRESSES: The meeting will be held at Wyndham Riverfront Hotel, Bacchus room, 701...

  20. Building America Expert Meeting: Combustion Safety

    Energy Technology Data Exchange (ETDEWEB)

    Brand, L.

    2013-03-01

    This is a meeting overview of 'The Best Approach to Combustion Safety in a Direct Vent World', held June 28, 2012, in San Antonio, Texas. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

  1. 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…

  2. 76 FR 67461 - Cosmetic Microbiological Safety Issues; Public Meeting

    Science.gov (United States)

    2011-11-01

    ...] Cosmetic Microbiological Safety Issues; Public Meeting AGENCY: Food and Drug Administration, HHS. ACTION... Administration (FDA) is announcing a public meeting entitled ``Cosmetic Microbiological Safety Issues.'' The... cosmetic microbiological safety and to suggest areas for the possible development of FDA guidance documents...

  3. Summary record of the 33. Meeting of NEA committee on reactor physics

    International Nuclear Information System (INIS)

    Martinelli, R.

    1991-01-01

    This paper is the summary record of the thirty-third meeting (Technical session) of the Nuclear Energy Agency Committee on Reactor Physics. A complete list of all the papers presented at this meeting is given in annex 4

  4. 76 FR 8372 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-02-14

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0070] Commercial Fishing Safety... Commercial Fishing Safety Advisory Committee (CFSAC) will meet in Portsmouth, Virginia to discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to the public...

  5. Unresolved safety issues summary. Aqua Book. Volume 6, No. 3

    International Nuclear Information System (INIS)

    Butts, J.

    1984-01-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the national laboratories and is prepared by the Office of Nuclear Reactor Regulation

  6. 77 FR 46555 - Motor Carrier Safety Advisory Committee: Public Meeting

    Science.gov (United States)

    2012-08-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee: Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety Advisory Committee (MCSAC...

  7. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  8. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Koponen, B.L.; Hampel, V.E.

    1982-10-21

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

  9. Second Meeting for Evaluation of the Nuclear Safety Convention

    International Nuclear Information System (INIS)

    2002-01-01

    This report presents the results of the Second Meeting for Evaluation of the Nuclear Safety Convention. the CSN. as the only competent Government organism on nuclear safety, represented Spain in the preparation of the national report and at the Review Meeting, acquiring a set of obligations for the next three years, until the holding of third meeting. (Author)

  10. IAEA advisory group meeting on completion of FENDL-1 and start of FENDL-2. Summary report

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1996-03-01

    The present report contains the summary of the IAEA Advisory Group Meeting on ''Completion of FENDL-1 and Start of FENDL-2'', held in Del Mar, California, USA, from 5 to 9 December 1995. The meeting was organized by the IAEA Nuclear Data Section with the cooperation and assistance of local organizers from TSI Research and the ITER Joint Central Team at San Diego. The FENDL library is a comprehensive collection of high-quality nuclear data, selected from the various existing national data libraries, covering the necessary nuclear input data for all physics and engineering aspects of the material development, design, operation and safety of the International Thermonuclear Experimental Reactor (ITER) project in its current Engineering Design Activities (EDA) phase and other fusion-related development projects. Summarized are results of the comprehensive integral data tests of FENDL-1 working libraries against available benchmark experiments performed in the framework of an international coordinated effort. Included are meeting conclusions and recommendations adopted for selection of evaluations for FENDL-2 together with a list of actions and time schedule. Attached are a detailed meeting agenda and a list of attendees. (author). Tabs

  11. 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...

  12. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  13. Project W-030 safety class upgrade summary report

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1998-01-01

    This document presents a summary of safety class criteria for the 241-AY/AZ Tank Farm primary ventilation system upgrade under Project W-030, and recommends acceptance of the system as constructed, based on a review of supporting documentation

  14. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-06-01

    The Summary Report of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors contains the Minutes of the Meeting (Part I); the papers which review the national programmes in the field of LMFBRs and other presentations at the Meeting (Part II); and the discussions on the review of the national programmes (Part III)

  15. 78 FR 23815 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2013-04-22

    .... 6] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety Committee (NECSC) Meeting. [[Page 23816

  16. 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

  17. 76 FR 62455 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-10-07

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-088)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel... Burch, Aerospace Safety Advisory Panel Administrative Officer, National Aeronautics and Space...

  18. 78 FR 1265 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-01-08

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-001] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel..., Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space Administration...

  19. Summary of the nuclear safety in operation

    International Nuclear Information System (INIS)

    2004-01-01

    This summary is a collection of general information about nuclear safety of PWR type reactors exploited by EDF. Teaching aid, this work has been conceived by operators for operators, it must not be considered nor used as a doctrine document with a regulatory or prescriptive characteristic. it summarizes the great principles of nuclear safety, places them in a global approach and shows their coherence. It consists in 6 chapters and 6 annexes. The news of this edition are the chapter 2 devoted to the safety management and the annexe 6 devoted to the principal teaching coming from the feedback. At the end a glossary explains the signs and abbreviations and an index allows to find themes in the memento text from keywords. (N.C.)

  20. 76 FR 19147 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2011-04-06

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-030)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel.... Kathy Dakon, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  1. 78 FR 56941 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-09-16

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: 13-114] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  2. 77 FR 25502 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-04-30

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (12-030)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel... FURTHER INFORMATION CONTACT: Ms. Harmony Myers, Aerospace Safety Advisory Panel Executive Director...

  3. 77 FR 38090 - Aerospace Safety Advisory Panel; Meeting.

    Science.gov (United States)

    2012-06-26

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-044] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  4. 75 FR 61219 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-10-04

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-116)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel... Dakon, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space Administration...

  5. 77 FR 58413 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2012-09-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-074] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announces a forthcoming meeting of the Aerospace Safety Advisory Panel.... Harmony Myers, Aerospace Safety Advisory Panel Executive Director, National Aeronautics and Space...

  6. 77 FR 60704 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2012-10-04

    ... regulations provide that FDA publish a quarterly list of available safety and effectiveness summaries of PMA...-0638] Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval... Administration (FDA) is publishing a list of premarket approval applications (PMAs) that have been approved. This...

  7. 75 FR 38532 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2010-07-02

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2010-M-0068...

  8. 78 FR 35284 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2013-06-12

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2013-M-0036... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

  9. 76 FR 31965 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2011-06-02

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2011-M-0034... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

  10. 75 FR 6407 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-02-09

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10- 020)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel... FURTHER INFORMATION CONTACT: Ms. Kathy Dakon, Aerospace Safety Advisory Panel Executive Director, National...

  11. France - Convention on Nuclear Safety. Sixth National report for the 2014 review meeting

    International Nuclear Information System (INIS)

    2013-07-01

    of Conduct on the Safety of Research Reactors, which reiterates most of the provisions of this present Convention. For this report, France took into account the lessons learned with the five previous reports: it is a self-standing document, which has been developed mostly on the basis of existing documents and reflects the views of the regulatory body and the licensees. Hence, for every chapter in which the regulatory body is not the only entity to express its own views, a three-fold structure was adopted: firstly a description of the regulations by the regulatory authority, followed by an overview presented by the licensees of their measures for regulatory compliance, and finally an analysis by the regulatory authority of licensee measures. This report is structured according to the Guidelines on National Reports, as revised at the special meeting of August 2012. The presentation progresses 'article by article', with each one giving rise to a separate chapter at the beginning of which the corresponding text of the Convention appears in a box with a half-tone background. After the introduction, which presents certain general aspects as well as national nuclear policy, the summary gives a description of the main changes that have taken place since the fifth national report and the safety prospects for the next three years. Part C covers general considerations (chapters 4 to 6), part D summarises general safety considerations (chapter 10 to 16), part F presents the safety of facilities (chapter 17 to 19), and finally part G presents international cooperation measures (chapter 20). The report is supplemented by eight appendices. With regard to the steps taken at the national level further to the TEPCO's Fukushima Daiichi nuclear power plant accident (hereinafter referred to as the Fukushima Daiichi accident), the Officers meeting of 29 October 2012 recommended including a general presentation in a sub-chapter of the Summary. Finally, further to the meeting of the

  12. 78 FR 36793 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-06-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-068] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel..., Huntsville, AL 35805 FOR FURTHER INFORMATION CONTACT: Ms. Harmony Myers, Aerospace Safety Advisory Panel...

  13. 75 FR 36697 - Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2010-06-28

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-071)] Aerospace Safety Advisory Panel... Aeronautics and Space Administration announce a forthcoming meeting of the Aerospace Safety Advisory Panel..., Room 116, Hampton, VA 23681. FOR FURTHER INFORMATION CONTACT: Ms. Kathy Dakon, Aerospace Safety...

  14. 78 FR 50422 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2013-08-19

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2013-M-0462...

  15. 75 FR 36099 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2010-06-24

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug...; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2009-M-0317...

  16. 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)

  17. Unresolved safety issues summary. Volume 3, Number 3. Aqua book

    International Nuclear Information System (INIS)

    1981-01-01

    The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  18. International Working Group on Fast Reactors Eight Annual Meeting, Vienna, Austria, 15-18 April 1975. Summary Report. Part II

    International Nuclear Information System (INIS)

    1975-07-01

    The Eighth Annual Meeting of the IAEA International Working Group on Past Reactors was held at the IAEA Headquarters in Vienna, Austria, from 15 to 18 April 1975. The Summary Report (Part I) contains the Minutes of the Meeting. The Summary Report (Part II) contains the papers which review the national programmes in the field of LMPBR’s and other presentations at the Meeting. The Summary Report (Part III) contains the discussions on the review of the national programmes

  19. Session summaries

    International Nuclear Information System (INIS)

    Sudo, Y.

    2002-01-01

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

  20. 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)

  1. 77 FR 60507 - Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting

    Science.gov (United States)

    2012-10-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Meeting of Compliance, Safety...

  2. Twenty-First Water Reaction Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 2, presents papers on severe accident research

  3. Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

  4. 78 FR 7460 - Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program

    Science.gov (United States)

    2013-02-01

    ...] Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of stakeholder meeting. SUMMARY: OSHA invites interested parties to attend an informal stakeholder meeting concerning Nationally Recognized Testing...

  5. 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

  6. Summary Report of Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Major Actinides

    International Nuclear Information System (INIS)

    Capote Noy, R.

    2013-09-01

    A summary is given of the Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Actinides. Experimental data and modelling methods on prompt fission neutron spectra were reviewed. Extensive technical discussions held on theoretical methods to calculate prompt fission spectra. Detailed coordinated research proposals have been agreed. Summary reports of selected technical presentations at the meeting are given. The resulting work plan of the Coordinated Research Programme is summarized, along with actions and deadlines. (author)

  7. Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-05-01

    The Summary Report of Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors contains the Minutes of the Meeting (Part I); the papers which review the national programmes in the field of LMFBRs and other presentations at the Meeting (Part II); and the discussions on the review of the national programmes (Part III)

  8. 78 FR 14314 - Towing Safety Advisory Committee; Meetings

    Science.gov (United States)

    2013-03-05

    ...: The Towing Safety Advisory Committee will meet in New York City, New York, March 21 and 22, 2013, to... the agenda in the SUPPLEMENTARY INFORMATION section below. The subcommittees will meet March 20, 2012, and work on seven assigned tasks listed in the referenced agenda. All meetings will be open to the...

  9. 78 FR 12065 - National Institute for Occupational Safety and Health Personal Protective Technology for...

    Science.gov (United States)

    2013-02-21

    ... Institute for Occupational Safety and Health Personal Protective Technology for Pesticide Handlers: Stakeholder Meeting AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers...: Notice of public meeting. SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of...

  10. Summary Report of Third Research Coordination Meeting on Minor Actinide Nuclear Reaction Data (MANREAD)

    International Nuclear Information System (INIS)

    Gunsing, Frank; Otsuka, Naohiko

    2010-12-01

    The Third Research Co-ordination Meeting of the MANREAD (Minor Actinides Neutron Reaction Data) Coordinated Research Project (CRP) was held at IAEA Headquarters in Vienna from 19 to 22 October 2010. A summary of the presentation, and the discussions which took place during the meeting, are reported here. In addition, a task assignment list of the experimental data assessment activities was agreed, and is provided together with the plan for future CRP activities. The Third Research Co-ordination Meeting of the MANREAD (Minor Actinides Neutron Reaction Data) Coordinated Research Project (CRP) was held at IAEA Headquarters in Vienna from 19 to 22 October 2010. A summary of the presentation, and the discussions which took place during the meeting, are reported here. In addition, a task assignment list of the experimental data assessment activities was agreed, and is provided together with the plan for future CRP activities. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

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

  12. 78 FR 77501 - NASA Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2013-12-23

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: 13-153] NASA Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of Meeting...

  13. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

  14. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

  15. 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)

  16. 78 FR 5243 - Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees

    Science.gov (United States)

    2013-01-24

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety...

  17. Building America Expert Meeting. Combustion Safety

    Energy Technology Data Exchange (ETDEWEB)

    Brand, Larry [Partnership for Advanced Residential Retrofit (PARR), Des Plaines, IL (United States)

    2013-03-01

    This is an overview of "The Best Approach to Combustion Safety in a Direct Vent World," held June 28, 2012, in San Antonio, TX. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

  18. IAEA consultants' meeting on benchmark validation of FENDL-1. Summary report

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1996-01-01

    The present report contains the Summary of the IAEA Consultants' Meeting on ''Benchmark Validation of FENDL-1'', held at Karlsruhe, Germany, from 17 to 19 October 1995. This meeting was organized by the IAEA Nuclear Data Section (NDS) with the co-operation and assistance of local organizers of the Forschungszentrum Karlsruhe, Germany. Summarized are the conclusions and the main results of extensive benchmarking of FENDL-1 by comparing experimental data from numerous number of fusion integral experiments, to analytical predictions based on discrete ordinates as well as Monte Carlo calculations. (author). 4 refs

  19. Occupational safety meets radiation protection

    International Nuclear Information System (INIS)

    Severitt, S.; Oehm, J.; Sobetzko, T.; Kloth, M.

    2012-01-01

    The cooperation circle ''Synergies in operational Security'' is a joint working group of the Association of German Safety Engineers (VDSI) and the German-Swiss Professional Association for Radiation Protection (FS). The tasks of the KKSyS are arising from the written agreement of the two associations. This includes work on technical issues. In this regard, the KKSyS currently is dealing with the description of the interface Occupational Safety / Radiation Protection. ''Ignorance is no defense'' - the KKSyS creates a brochure with the working title ''Occupational Safety meets radiation protection - practical guides for assessing the hazards of ionizing radiation.'' The target groups are entrepreneurs and by them instructed persons to carry out the hazard assessment. Our aim is to create practical guides, simple to understand. The practical guides should assist those, who have to decide, whether an existing hazard potential through ionizing radiation requires special radiation protection measures or whether the usual measures of occupational safety are sufficient. (orig.)

  20. 75 FR 14471 - Advisory Committee on Construction Safety and Health (ACCSH)

    Science.gov (United States)

    2010-03-25

    ... and Health (ACCSH) and ACCSH Work Group meetings. SUMMARY: ACCSH will meet April 14 and 16, 2010, in... Safety and Health in the formulation of standards affecting the construction industry and on policy matters arising in the administration of the safety and health provisions of the Contract Work Hours and...

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

    International Nuclear Information System (INIS)

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

    2009-08-01

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

  2. 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)

  3. 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)

  4. 75 FR 78775 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2010-12-16

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0012] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH subgroup meetings. SUMMARY: The National...

  5. Fast reactor safety: proceedings of the international topical meeting. Volume 2

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

  6. 75 FR 70955 - Advisory Committee on the Medical Uses of Isotopes: Meeting Notice

    Science.gov (United States)

    2010-11-19

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on the Medical Uses of Isotopes: Meeting Notice AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Notice of meeting. SUMMARY: The U.S. Nuclear... the draft safety culture policy statement for medical licensees. A copy of the agenda for the meeting...

  7. Circumpolar Biodiversity Monitoring Programme: Coastal Expert Workshop meeting summary

    Science.gov (United States)

    Thomson, L.; McLennan, Donald; Anderson, Rebecca D.; Wegeberg, S.; Pettersvik Arvnes, Maria; Sergienko, Liudmila; Behe, Carolina; Moss-Davies, Pitseolak; Fritz, S.; Christensen, T.; Price, C.

    2016-01-01

    The Coastal Expert Workshop brought together a diverse group of coastal experts with the common goal of developing a biodiversity monitoring program for coastal ecosystems across the circumpolar Arctic. Meeting participants, including northern residents, industry and Non-Governmental Organization (NGO) representatives, scientists, and government regulators from across the circumpolar Arctic, gathered at the Lord Elgin Hotel in Ottawa from March 1 to 3, 2016, to discuss current biodiversity monitoring efforts, understand key issues facing biodiversity in the Arctic coastal areas and suggest monitoring indicators, or Focal Ecosystem Components, for the program. A Traditional Knowledge Holders meeting was held on February 29, 2016 in conjunction with the workshop. The following document provides a summary of the workshop activities and outcomes, and will be followed by a more complete Workshop Report.

  8. Proceedings of the Nuclear Criticality Technology Safety Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  9. 77 FR 64549 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-10-22

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and a NACOSH Work Group. SUMMARY: NACOSH will meet...

  10. Summary report of 2. research coordination meeting on Minor Actinide Neutron Reaction Data (MANREAD)

    International Nuclear Information System (INIS)

    Nagai, Y.; Mengoni, A.

    2009-07-01

    The second Research Co-ordination Meeting of the MANREAD (Minor Actinides Neutron Reaction Data) was held at the IAEA Headquarters in Vienna from 31 March to 3 April 2009. A summary of the discussion which took place at the meeting is reported here together with a list of the main outcomes and recommendations produced by the RCM participants. (author)

  11. Meeting of the high committee for nuclear safety transparency and information. Proceedings of the June 18, 2008 meeting

    International Nuclear Information System (INIS)

    2008-01-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main topics: 1 - the organization and stakes of nuclear safety and radiation protection in France, 2 - the plutonium imports and transports from England to France and their conformability with respect to the maritime, nuclear safety and nuclear security regulations, 3 - the role and operation of the HCTISN. This document is the proceedings of this meeting. (J.S.)

  12. Specialists' meeting on sodium boiling noise detection. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-01-01

    The purpose of the meeting was to review and discuss methods available for detection of the initial stage of accidents in fast reactors, with most attention on reliable detection by acoustic techniques, which could provide a valuable addition to the safety protection. Results obtained from reactor experiments were also discussed and recommendations made for future developments. The meeting was divided into five technical sessions as follows: Signals from sodium boiling; Transmission of acoustic waves and background noise; Detection techniques; Reactor experiments; and Future requirements.

  13. Specialists' meeting on sodium boiling noise detection. Summary report

    International Nuclear Information System (INIS)

    1982-01-01

    The purpose of the meeting was to review and discuss methods available for detection of the initial stage of accidents in fast reactors, with most attention on reliable detection by acoustic techniques, which could provide a valuable addition to the safety protection. Results obtained from reactor experiments were also discussed and recommendations made for future developments. The meeting was divided into five technical sessions as follows: Signals from sodium boiling; Transmission of acoustic waves and background noise; Detection techniques; Reactor experiments; and Future requirements

  14. 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)

  15. Third research coordination meeting on reference database for neutron activation analysis. Summary report

    International Nuclear Information System (INIS)

    Kellett, M.A.

    2009-12-01

    The third meeting of the Co-ordinated Research Project on 'Reference Database for Neutron Activation Analysis' was held at the IAEA, Vienna from 17-19 November 2008. A summary of presentations made by participants is given, reports on specific tasks and subsequent discussions. With the aim of finalising the work of this CRP and in order to meet initial objectives, outputs were discussed and detailed task assignments agreed upon. (author)

  16. 77 FR 22358 - Occupational Safety and Health Administration

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration Preparations for the 23rd Session of the UN Sub-Committee of Experts on the Globally Harmonized System of Classification and...: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of public meeting. SUMMARY: OSHA...

  17. 75 FR 21602 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-04-26

    ... OSTWG is tasked with evaluating industry efforts to promote a safe online environment for children. The... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  18. 77 FR 31398 - National Advisory Committee on Occupational Safety and Health (NACOSH)

    Science.gov (United States)

    2012-05-25

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... on Occupational Safety and Health (NACOSH) and NACOSH Work Groups. SUMMARY: NACOSH will meet June 20...

  19. 78 FR 49262 - Sunshine Act Meeting

    Science.gov (United States)

    2013-08-13

    ... the importance of robust oversight to sustain long-term improvements. CONTACT PERSON FOR FURTHER... Board's Washington office and at DOE's public reading room at the DOE Federal Building, 1000... Safety Board. ACTION: Notice of Public Meeting and Hearing. SUMMARY: Pursuant to the provisions of the...

  20. First IAEA research co-ordination meeting on 'Tritium inventory in fusion reactors'. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2003-02-01

    The proceedings and conclusions of the first Research Co-ordination Meeting on 'Tritium Inventory in Fusion Reactors', held on November 4-6, 2002 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of the presentations made by the meeting participants and the specific goals set by the participants of the Co-ordinated Research Project (CRP). (author)

  1. 75 FR 1338 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-01-11

    ... promote a safe online environment for children. The Act requires the OSTWG to report its findings and... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  2. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  3. Thirteenth water reactor safety research information meeting: proceedings Volume 1

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

    This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

  4. Summary Report of Consultants' Meeting on Auger Electron Emission Data Needs for Medical Applications

    International Nuclear Information System (INIS)

    Noy, Roberto Capote; Chung, Hyun Kyung; Bartschat, Klaus; Dong, Chenzhong; Jonsson, Per; Kibedi, Tibor; Kondev, Filip G.; Nikjoo, Hooshang; Palffy, Adriana

    2013-11-01

    A summary is given of a Consultants' Meeting on 'Auger Electron Emission Data Needs for Medical Applications'. Participants assessed and reviewed detailed atomic and nuclear data needs for a number of Auger emitters deemed as potentially suitable for applications in nuclear medicine and radiotherapy. Technical discussions are described in this report, along with recommendations for future work, along with recommendations for future work. Presentations by the consultants at the meeting are available at http://www-nds.iaea.org/index-meeting-crp/CM-Auger-2013/. (author)

  5. 78 FR 60290 - Availability of Masked and De-identified Non-Summary Safety and Efficacy Data; Reopening of...

    Science.gov (United States)

    2013-10-01

    ..., 2013, on the following topics: (1) What factors should be considered in masking study data (e.g., data...] Availability of Masked and De-identified Non-Summary Safety and Efficacy Data; Reopening of Comment Period... of Masked and De- identified Non-Summary Safety and Efficacy Data; Request for Comments,'' which...

  6. 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)

  7. 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)

  8. IAEA specialists' meeting on power ramping and cycling behaviour of water reactor fuel. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-06-01

    At its fourth Annual Meeting, the IAEA International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended that the Agency should hold a second Specialists' Meeting on 'Power Ramping and Cycling Behaviour of Water Reactor Fuel'. As research activities related to power ramping and cycling of water reactor fuel have been pursued vigorously, it was the objective of this meeting to review and discuss today's State of the Art and current understanding of water reactor fuel behaviour related to this these. Emphasis should be on practical experience and experimental investigations. The meeting was organised in five sessions: Power ramping and power cycling programs in power and and research reactors; Experimental methods; Power ramping and cycling results; Investigations and results of separate effects, especially related to PCI, defect mechanism, mechanical response, fuel design, and specially related to fission gas release; Operational strategies, recommendations and economic implications. The session chairmen, together with the speakers, prepared and presented reports with summary, conclusions and recommendations of the individual sessions. These reports are added to this summary report.

  9. IAEA specialists' meeting on power ramping and cycling behaviour of water reactor fuel. Summary report

    International Nuclear Information System (INIS)

    1983-06-01

    At its fourth Annual Meeting, the IAEA International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended that the Agency should hold a second Specialists' Meeting on 'Power Ramping and Cycling Behaviour of Water Reactor Fuel'. As research activities related to power ramping and cycling of water reactor fuel have been pursued vigorously, it was the objective of this meeting to review and discuss today's State of the Art and current understanding of water reactor fuel behaviour related to this these. Emphasis should be on practical experience and experimental investigations. The meeting was organised in five sessions: Power ramping and power cycling programs in power and and research reactors; Experimental methods; Power ramping and cycling results; Investigations and results of separate effects, especially related to PCI, defect mechanism, mechanical response, fuel design, and specially related to fission gas release; Operational strategies, recommendations and economic implications. The session chairmen, together with the speakers, prepared and presented reports with summary, conclusions and recommendations of the individual sessions. These reports are added to this summary report

  10. Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

  11. 77 FR 47864 - Ocean Energy Safety Advisory Committee (OESC); Notice of Meeting

    Science.gov (United States)

    2012-08-10

    ...), Interior. ACTION: Notice of meeting. SUMMARY: OESC will meet at the Anchorage Marriott Downtown Hotel in..., from 8 a.m. to 1 p.m. ADDRESSES: Anchorage Marriott Downtown Hotel, 820 West 7th Avenue, Anchorage... the Office of Management and Budget's Circular No. A-63, Revised. Dated: August 1, 2012. James A...

  12. 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)

  13. 75 FR 80083 - Advisory Committee on the Medical Uses of Isotopes: Meeting Notice

    Science.gov (United States)

    2010-12-21

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on the Medical Uses of Isotopes: Meeting Notice AGENCY: U.S. Nuclear Regulatory Commission. ACTION: Notice of Meeting. SUMMARY: The U.S. Nuclear... the draft safety culture policy statement for medical licensees. Contingent upon the outcome of the...

  14. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

    International Nuclear Information System (INIS)

    1995-10-01

    There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

  15. Summary report of consultants' meeting on IAEA international database on irradiated nuclear graphite properties

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2007-06-01

    The '9th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 26-27 March 2007 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)

  16. Summary Record of the 15th Meeting of the Working Group on Risk Assessment (WGRISK)

    International Nuclear Information System (INIS)

    2015-01-01

    The main mission of the working group on risk assessment (WGRISK) is to advance the understanding and utilisation of probabilistic safety assessment (PSA) in ensuring the continued safety of nuclear installations in member countries. While PSA methodology has matured greatly over the years, further work is required. WGRISK has been active in several of these areas, including: human reliability; software reliability; low power and shutdown risk. In order to maintain a current perspective, the working group collaborates and assists other working groups within the CSNI, such as operating experience and organisational factors as well as keeping close co-ordination with other international organisations. Over the past twenty years, the NEA PWG5 and now WGRISK have looked at the technology and methods used for identifying contributors to risk and assessing their importance. Work during much of this period was concentrated on Level-1 PSA methodology. In recent years the focus has shifted into more specific PSA methodologies and risk-informed applications. This document summarizes the content of the 15. Meeting of WGRISK: - presentation of the new WGRISK Bureau, - Approval of the 14. WGRISK Meeting Summary Record [NEA/SEN/SIN/WGRISK (2013)1], - Use and Development of PSA in NEA Member Countries and by other International Organisations, - Report by the WGRISK Secretariat on the current WGRISK programme of work, actions taken by CSNI and CNRA and other recent developments in OECD/NEA, - Development of BPGs on failure mode taxonomy for reliability assessment of digital I and C systems for PSA [Task 2010-3], - Update Use of OECD Data Project Products in PSA [Task 2011-1], - Status report on the common WGHOF/WGRISK HRA Task, - Outcome on the International Workshop on PSA of Natural External Hazards Including Earthquakes, April 2014 [Task 2012-1], - Status report on the International Workshop on Fire PRA [Task 2012-2], - PSA insights relating to the loss of electrical sources

  17. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  18. Proceedings of the nuclear criticality technology safety project

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

  19. Summary report of first research coordination meeting on Minor Actinide Nuclear Reaction Data (MANREAD)

    International Nuclear Information System (INIS)

    Kaeppeler, F.; Mengoni, A.

    2008-09-01

    The first Research Co-ordination Meeting of the MANREAD (Minor Actinides Neutron Reaction Data) was held at the IAEA Headquarters in Vienna from 19 to 23 November 2007. A summary of the discussion which took place at the meeting is reported here. In addition, a task assignment list of the experimental data assessment activities was agreed, and is provided together with the plan for future CRP activities. (author)

  20. 77 FR 73734 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-11

    .... 5] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of a Northeast Corridor Safety... Committee is made up of stakeholders operating on the [[Page 73735

  1. Working group on VVER safety analysis - report of the 2010 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2010-01-01

    The AER Working Group D on WWER reactor safety analysis held its nineteenth meeting in Pisa, Italy, during the period 15-16 April, 2010. The meeting was hosted by the San Piero a Grado Nuclear Research Group of the University of Pisa and was held in conjunction with the second workshop on the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP and the fourth workshop on the OECD Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs. Altogether 12 participants attended the meeting of the working group D, 8 from AER member organizations and 4 guests from non-member organization. The co-ordinator of the working group, Mr. S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics:-Code validation and benchmarking including the calculation of the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP;-Safety analyses and code developments;-Future activities A list of the participants and a list of the handouts distributed at the meeting are attached to the report. The corresponding PDF-files can be obtained from the chairman. (Author)

  2. Progress summary of the Chernobyl accident

    International Nuclear Information System (INIS)

    Iddekinge, F.W. van

    1986-01-01

    Based on two IAEA documents (the report of the USSR State Committee on the Utilization of Atomic Energy named 'The accident at the Chernobyl nuclear power plant and its consequences' prepared for the IAEA Experts Meeting held in Vienna on 25-29 August, 1986 and the INSAG (International Nuclear Safety Advisory Group) summary report on the Post-accident review meeting on the Chernobyl accident, drawn up in Vienna from August 30 until September 5, 1986, this publication tries to present a logic relation between the special features of the RMBK-1000 LWGR, the cause of the accident, and the technical countermeasures. (Auth.)

  3. 76 FR 80873 - Food Source Attribution; Public Meeting

    Science.gov (United States)

    2011-12-27

    ... outline or summary of an oral presentation, contact: Juanita Yates, FDA, Center for Food Safety and Applied Nutrition, telephone: (240) 402-1731, email: [email protected] . To request special... the meeting, contact Dr. David Goldman, Assistant Administrator, Office of Public Health Science, USDA...

  4. 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)

  5. 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)

  6. Convention on nuclear safety 2012 extra ordinary meeting. The Swedish National Report

    International Nuclear Information System (INIS)

    2012-01-01

    During the 5th Review Meeting of the Convention on Nuclear Safety (CNS), the Contracting Parties in attendance agreed to hold an Extraordinary Meeting in August 2012 with the aim to enhance safety through reviewing and sharing lessons learned and actions taken by Contracting Parties in response to events at TEPCO Fukushima Dai-ichi. It was agreed that a brief and concise National Report should be developed by each Contracting Party to support the Extraordinary Meeting. This report should be submitted three months prior to the meeting to the Secretariat via the Convention-secured website for peer review by other Contracting Parties. It was also agreed that the Contracting Parties should organize their reports by topics that cross the boundaries of multiple CNS Articles. Each National Report should provide specific information on these topics to address the lessons learned and activities undertaken by each Contracting Party. The National Report should include a description of the activities the Contracting Party has completed and any activities it intends to complete along with scheduled completion dates. The present report is therefore structured in accordance with the guidance given by the General Committee for CNS. In Chapter 0, a brief description of Swedish nuclear power plants is given with an emphasis on measures that have been taken gradually as a result of new knowledge and experience. The following chapters deal with the six topics, which are: 1) External events, 2) Design issues, 3) Severe accident management and recovery, 4) National organizations, 5) Emergency preparedness and response and post-accident management, and 6) International cooperation. Each chapter concludes with a table illustrating a high-level summary of the items identified. To clarify the relationship between the text and table contained in each chapter, the parts of the text appearing in the table are underlined. Furthermore, the text of some sections/subsections in different chapters

  7. 78 FR 32010 - Pipeline Safety: Public Workshop on Integrity Verification Process

    Science.gov (United States)

    2013-05-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Hazardous Materials Safety Administration, DOT. ACTION: Notice of public meeting. SUMMARY: This notice is announcing a public workshop to be held on the concept of ``Integrity Verification Process.'' The Integrity...

  8. Phases of QCD: Summary of the Rutgers Long Range Plan Town Meeting, January 12-14, 2007

    International Nuclear Information System (INIS)

    Jacobs, Peter; Kharzeev, Dmitri; Muller, Berndt; Nagle, Jamie; Rajagopal, Krishna; Vigdor, Steve

    2007-01-01

    This White Paper summarizes the outcome of the Town Meeting on Phases of QCD that took place January 12-14, 2007 at Rutgers University, as part of the NSAC 2007 Long Range Planning process. The meeting was held in conjunction with the Town Meeting on Hadron Structure, including a full day of joint plenary sessions of the two meetings. Appendix A.1 contains the meeting agenda. This Executive Summary presents the prioritized recommendations that were determined at the meeting. Subsequent chapters present the essential background to the recommendations. While this White Paper is not a scholarly article and contains few references, it is intended to provide the non-expert reader

  9. Phases of QCD: Summary of the Rutgers Long Range Plan Town Meeting, January 12-14, 2007

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, Peter; Kharzeev, Dmitri; Muller, Berndt; Nagle, Jamie; Rajagopal, Krishna; Vigdor, Steve

    2007-05-14

    This White Paper summarizes the outcome of the Town Meeting on Phases of QCD that took place January 12-14, 2007 at Rutgers University, as part of the NSAC 2007 Long Range Planning process. The meeting was held in conjunction with the Town Meeting on Hadron Structure, including a full day of joint plenary sessions of the two meetings. Appendix A.1 contains the meeting agenda. This Executive Summary presents the prioritized recommendations that were determined at the meeting. Subsequent chapters present the essential background to the recommendations. While this White Paper is not a scholarly article and contains few references, it is intended to provide the non-expert reader

  10. 78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

    Science.gov (United States)

    2013-03-20

    ... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

  11. 77 FR 20690 - Northeast Corridor Safety Committee; Notice of Meeting

    Science.gov (United States)

    2012-04-05

    .... 4] Northeast Corridor Safety Committee; Notice of Meeting AGENCY: Federal Railroad Administration (FRA), Department of Transportation (DOT). ACTION: Announcement of the Northeast Corridor Safety... NECSC is made up of stakeholders operating on the Northeast Corridor (NEC), and the purpose of the...

  12. 78 FR 4829 - Codex Alimentarius Commission: Meeting of the Codex Committee on Fats and Oils

    Science.gov (United States)

    2013-01-23

    ... will be held in Langkawi, Malaysia, February 25-March 1, 2013. The Under Secretary for Food Safety and... DEPARTMENT OF AGRICULTURE Food Safety and Inspection Service [Docket No. FSIS-2012-0055] Codex... for Food Safety, USDA. ACTION: Notice of public meeting and request for comments. SUMMARY: The Office...

  13. Phase-space database for external beam radiotherapy. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Capote, R.; Jeraj, R.; Ma, C.M.; Rogers, D.W.O.; Sanchez-Doblado, F.; Sempau, J.; Seuntjens, J.; Siebers, J.V.

    2006-01-01

    A summary is given of a Consultants' Meeting assembled to discuss and recommend actions and activities to prepare a Phase-space Database for External Beam Radiotherapy. The new database should serve to disseminate phase-space data of those accelerators and 60 Co units used in radiotherapy through the compilation of existing data that have been properly validated. Both the technical discussions and the resulting work plan are described, along with the detailed recommendations for implementation. The meeting was jointly organized by NAPC-Nuclear Data Section and NAHU-Dosimetry and Medical Radiation Physics Section. (author)

  14. Key issues for passive safety

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1996-01-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ''review paper'' as such and only record the highlights. (author)

  15. Key issues for passive safety

    Energy Technology Data Exchange (ETDEWEB)

    Hayns, M R [AEA Technology, Harwell, Didcot (United Kingdom). European Institutions; Hicken, E F [Forschungszentrum Juelich GmbH (Germany)

    1996-12-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ``review paper`` as such and only record the highlights. (author).

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

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1999-01-01

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

  17. Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

    2008-07-01

    'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

  18. Visual Impairment/Intracranial Pressure Research Clinical Advisory Panel (RCAP) Meeting. [Summary Report

    Science.gov (United States)

    Villarreal, Jennifer

    2014-01-01

    The Visual Impairment/Intracranial Pressure (VIIP) Research and Clinical Advisory Panel convened on December 1, 2014 at the ISS Conference Facility in Houston. The panel members were provided updates to the current clinical cases and treatment plans along with the latest research activities (http://humanresearchroadmap.nasa.gov/Risks/?i=105) and preliminary study results. The following is a summary of this meeting.

  19. 78 FR 17415 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2013-03-21

    ... its decision. The regulations provide that FDA publish a quarterly list of available safety and..., FDA-2012-M-1183, and FDA-2012-M-1184] Medical Devices; Availability of Safety and Effectiveness.... SUMMARY: The Food and Drug Administration (FDA) is publishing a list of premarket approval applications...

  20. Specialists' meeting on passive and active safety features of LMFRs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics.

  1. Specialists' meeting on passive and active safety features of LMFRs

    International Nuclear Information System (INIS)

    1991-01-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics

  2. Development of a reference database for ion beam analysis. Summary report of the first research coordination meeting

    International Nuclear Information System (INIS)

    Vickridge, I.; Schwerer, O.

    2006-01-01

    A summary is given of the First Research Coordination Meeting on the Development of a Reference Database for Ion Beam Analysis, including background information, objectives, recommendations for measurements, and a list of tasks assigned to participants. The next research co-ordination meeting will be held in May 2007. (author)

  3. Brighter future predicted at nuclear meetings in Chicago

    International Nuclear Information System (INIS)

    Stein, H.

    1993-01-01

    This article discusses the future of nuclear power in the United States and the rest of the world. It is a summary of a meeting of the American Nuclear Society/European Nuclear Society in Chicago. Some topics discussed include advanced reactor design, public relations, and nuclear safety

  4. Improving operational safety management through probabilistic safety assessment on personal computers

    International Nuclear Information System (INIS)

    1988-10-01

    The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

  5. 17. meeting of the Society for Reactor Safety. Proceedings

    International Nuclear Information System (INIS)

    1994-06-01

    An autonomous and independent reactor safety research in Germany is indispensable. Three out of the four papers of the meeting deal with the protective aim concept of NPP. Deterministic safety assessment during periodic in-service inspections, a new generation of information engineering, and the incorporation of serious accidents in the containment design of new reactors are considered in detail. (DG) [de

  6. 19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

    Science.gov (United States)

    Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

    2002-01-01

    This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

  7. 75 FR 34520 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-06-17

    ... Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting AGENCY: Office of the Secretary of... Secretary of Transportation, announces a meeting of the FAAC Aviation Safety Subcommittee, which will be... of the global economy. The Aviation Safety Subcommittee will develop a list of priority safety issues...

  8. The Fusion Evaluated Nuclear Data Library (FENDL). Summary Report of an IAEA Consultants’ Meeting

    International Nuclear Information System (INIS)

    Fleming, Michael; Trkov, Andrej

    2016-08-01

    The Consultants’ Meeting on the Fusion Evaluated Nuclear Data Library (FENDL) was held at the IAEA Headquarters in Vienna from 1 to 4 August 2016. A summary of the presentations, discussions, actions and strategies for the future library versions and distributions are provided in this report. (author)

  9. Computer aided safety analysis 1989

    International Nuclear Information System (INIS)

    1990-04-01

    The meeting was conducted in a workshop style, to encourage involvement of all participants during the discussions. Forty-five (45) experts from 19 countries, plus 22 experts from the GDR participated in the meeting. A list of participants can be found at the end of this volume. Forty-two (42) papers were presented and discussed during the meeting. Additionally an open discussion was held on the possible directions of the IAEA programme on Computer Aided Safety Analysis. A summary of the conclusions of these discussions is presented in the publication. The remainder of this proceedings volume comprises the transcript of selected technical papers (22) presented in the meeting. It is the intention of the IAEA that the publication of these proceedings will extend the benefits of the discussions held during the meeting to a larger audience throughout the world. The Technical Committee/Workshop on Computer Aided Safety Analysis was organized by the IAEA in cooperation with the National Board for Safety and Radiological Protection (SAAS) of the German Democratic Republic in Berlin. The purpose of the meeting was to provide an opportunity for discussions on experiences in the use of computer codes used for safety analysis of nuclear power plants. In particular it was intended to provide a forum for exchange of information among experts using computer codes for safety analysis under the Technical Cooperation Programme on Safety of WWER Type Reactors (RER/9/004) and other experts throughout the world. A separate abstract was prepared for each of the 22 selected papers. Refs, figs tabs and pictures

  10. FAST FLUX TEST FACILITY DRIVER FUEL MEETING

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1966-06-01

    The Pacific Northwest Laboratory has convened this meeting to enlist the best talents of our laboratories and industry in soliciting factual, technical information pertinent to the Pacific Northwest's Laboratory's evaluation of the potential fuel systems for the Fast Flux Test Facility. The particular factors emphasized for these fuel systems are those associated with safety, ability to meet testing objectives, and economics. The proceedings includes twenty-three presentations, along with a transcript of the discussion following each, as well as a summary discussion.

  11. Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety

    International Nuclear Information System (INIS)

    1997-01-01

    The fifth international topical meeting on nuclear thermohydraulics, operations and safety was convened in Beijing in April 14-18, 1997. The topical meeting was sponsored by the Chinese Nuclear Society and cosponsored by American Nuclear Society, Atomic Energy Society of Japan, American Society of Mechanical Engineers, Canada Nuclear Society, Korean Nuclear Society, Mexican Nuclear Society, Nuclear Society of Slovenia and Spanish Nuclear Society. There were 262 articles were published in the meeting. They are related nuclear power thermohydraulics, operations and safety

  12. Proceedings of a topical meeting on safety of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1996-01-01

    The topical meeting on the safety of the nuclear fuel cycle is composed of 17 papers grouped into four sessions which titles are: operational safety in nuclear fuel facilities; safety criteria and regulatory philosophy; plant hazard analysis and mitigation; plant experience and emergency planning

  13. Final summary report of the Nordic Nuclear Safety Research Program 1998-2001

    International Nuclear Information System (INIS)

    Bennerstedt, T.

    2002-11-01

    The results of the 1998 - 2001 NKS program are presented in the form of executive summaries, highlighting the conclusions, recommendations and other findings and results of the six projects carried out during that period. The titles of the six projects are: Risk assessment and strategies for safety (NKS/SOS-1); Reactor safety (NKS/SOS-2); Radioactive waste (NKS/SOS-3); Nuclear Emergency preparedness (NKS/BOK-1); Radiological and environmental consequences (NKS/BOK-2); Nuclear threats from Nordic surroundings (NKS/SBA-1) (ln)

  14. 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)

  15. 33 CFR 96.230 - What objectives must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... management system meet? 96.230 Section 96.230 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.230 What objectives must a safety...

  16. Specialists' meeting on theoretical modelling of LMFBR fuel pin behaviour. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-12-01

    The purpose of the meeting was to provide an opportunity for exchanging views of theoretical modelling of LMFBR fuel pin behaviour and to summarise the IWGFR member countries' knowledge in this field. The special emphasis was placed on normal operating conditions. The technical part of the meeting was divided into six sessions, as follows: An overview of fuel modelling studies; Key factors and basic phenomena relevant to fuel pin behaviour modelling; Application to steady state operation and normal transients; Experimental validation through pins in service and specific irradiation experiments; Advanced fuels; and Brief review of existing codes. During the meeting, papers were presented by the delegates on behalf of their countries or organization. The papers, which are included in this report, were either in the form of a general survey of the subject, or on specific technical subjects. In each subject area presentations appropriate to the subject were made from the submitted papers. The presentations were followed by discussions of the questions raised and summary is made.

  17. Specialists' meeting on theoretical modelling of LMFBR fuel pin behaviour. Summary report

    International Nuclear Information System (INIS)

    1979-12-01

    The purpose of the meeting was to provide an opportunity for exchanging views of theoretical modelling of LMFBR fuel pin behaviour and to summarise the IWGFR member countries' knowledge in this field. The special emphasis was placed on normal operating conditions. The technical part of the meeting was divided into six sessions, as follows: An overview of fuel modelling studies; Key factors and basic phenomena relevant to fuel pin behaviour modelling; Application to steady state operation and normal transients; Experimental validation through pins in service and specific irradiation experiments; Advanced fuels; and Brief review of existing codes. During the meeting, papers were presented by the delegates on behalf of their countries or organization. The papers, which are included in this report, were either in the form of a general survey of the subject, or on specific technical subjects. In each subject area presentations appropriate to the subject were made from the submitted papers. The presentations were followed by discussions of the questions raised and summary is made

  18. 2nd (final) IAEA research co-ordination meeting on 'charge exchange cross section data for fusion plasma studies'. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2001-11-01

    The proceedings and conclusions of the 2nd Research Co-ordination Meeting on 'Charge Exchange Cross Section Data for Fusion Plasma Studies', held on September 25 and 26, 2000 at the IAEA Headquarters in Vienna, are briefly described. This report includes a summary of the presentations made by the meeting participants and a review of the accomplishments of the Co-ordinated Research Project (CRP). In addition, short summaries from the participants are included indicating the specific research completed in support of this CRP. (author)

  19. 75 FR 44998 - The Future of Aviation Advisory Committee (FAAC) Aviation Safety Subcommittee; Notice of Meeting

    Science.gov (United States)

    2010-07-30

    ... evolving transportation needs, challenges, and opportunities of the global economy. The Aviation Safety... activities associated with the list of priority safety issues developed during the first meeting. The subcommittee will also develop a work plan for future meetings. DATES: The meeting will be held on August 24...

  20. Hanford Site Environmental Safety and Health Fiscal Year 2001 Budget-Risk management summary

    Energy Technology Data Exchange (ETDEWEB)

    REEP, I.E.

    1999-05-12

    The Hanford Site Environment, Safety and Health (ES&H) Budget-Risk Management Summary report is prepared to support the annual request to sites in the U.S. Department of Energy (DOE) Complex by DOE, Headquarters. The request requires sites to provide supplementary crosscutting information related to ES&H activities and the ES&H resources that support these activities. The report includes the following: (1) A summary status of fiscal year (FY) 1999 ES&H performance and ES&H execution commitments; (2)Status and plans of Hanford Site Office of Environmental Management (EM) cleanup activities; (3) Safety and health (S&H) risk management issues and compliance vulnerabilities of FY 2001 Target Case and Below Target Case funding of EM cleanup activities; (4) S&H resource planning and crosscutting information for FY 1999 to 2001; and (5) Description of indirect-funded S&H activities.

  1. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-07-01

    The Summary Report - Part II of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - includes reports on development of fast reactors in France from 1977 to 1978; review of the activities related to fast reactors in Germany; status of fast breeder reactors development in Belgium and Netherlands; status of activities related to fast reactors in USSR, Japan USA, UK and Italy.

  2. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part II

    International Nuclear Information System (INIS)

    1978-07-01

    The Summary Report - Part II of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - includes reports on development of fast reactors in France from 1977 to 1978; review of the activities related to fast reactors in Germany; status of fast breeder reactors development in Belgium and Netherlands; status of activities related to fast reactors in USSR, Japan USA, UK and Italy

  3. Summary Report of the Consultants' Meeting on EXFOR Data in Resonance Region and Spectrometer Response Function

    International Nuclear Information System (INIS)

    Gunsing, F.; Schillebeeckx, P.; Semkova, V.

    2013-12-01

    The Consultants' Meeting 'EXFOR Data in Resonance Region and Spectrometer Response Function' was held at the IAEA Headquarters in Vienna from 8 to 10 October 2013. A summary of the presentations and discussions that took place during the meeting is reported here. The participants have agreed on recommendations on data reporting for EXFOR and on the need of documenting spectrometer response functions. Recommendations are given for experimentalists, for compilers, and for evaluators. (author)

  4. Public meeting on radiation safety for industrial radiographerss: remarks, questions and answers at five NRC regional meetings

    International Nuclear Information System (INIS)

    1978-11-01

    Over the past several years thenumber of radiation overexposures experienced in the radiography industry has been higher than for any other single group of NRC licensees. To inform radiography licensees of NRC's concern fo these recurring overexposure incidents, NRC staff representatives met with licensees in a series of five regional meetings. At these meetings the staff presented prepared remarks and answered questions on NRC regulations and operations. The main purposes of the meetings were to express NRC's concern for the high incidence of overexposures, and to open a line of communication between the NRC and radiography licensees in an effort to achieve the common goal of improved radiation safety. The remarks presented by the staff and subjects discussed at these meetings included: the purpose, scope, findings and goals of the NRC inspection program; ways and means of incorporating safety into radiography operations; and case histories of overexposure incidents, with highlights of the causes and possible preventions. At each of the regional meetings the staff received a request for a copy of the prepared remarks and a consolidation of the questions and answers that were discussed. This document includes that information, and a copy is being provided to each organizaion or firm attending the regional meetings. Requests for other copies should be made in accordance with the directions printed inside the front cover of this document

  5. 77 FR 34123 - Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines

    Science.gov (United States)

    2012-06-08

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0100] Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines AGENCY: Office of Pipeline Safety, Pipeline and Hazardous Materials Safety Administration, DOT. ACTION...

  6. Summary Record of the Sixth Meeting of Records, Knowledge and Memory (RK and M) Across Generations

    International Nuclear Information System (INIS)

    2014-01-01

    Preservation of Records, Knowledge and Memory (RK and M) across Generations is an initiative under the RWMC in the area of knowledge consolidation and transfer. Disposal in engineered facilities built in stable, deep geological formations is the reference means for permanently isolating long-lived radioactive waste from the biosphere. However, there is no intention to forgo, at any time, knowledge and awareness either of the repository or of the waste that it contains. The cultural dimension of preserving RK and M is an important subject. Overall, long-term preservation of RK and M is a multidisciplinary work area in which much learning is expected over the coming years. This is the task of the RWMC's RK and M initiative. A major outcome will be a menu-driven document that - the RK and M Wiki - that will allow people to identify the elements of a strategic action plan for RK and M preservation. This document is a summary record of the Sixth Meeting of Records, Knowledge and Memory (RK and M) Across Generations. The summary is made of 8 items: 1 - Introduction (C. Pescatore): Welcome and opening remarks, Review and adoption of the agenda, Aim of this meeting, Status report, Report from RepMet meeting; 2 - Finalising Phase-II: Updating the Set of Essential Records (SER) proposal (C. Mays), Updates to the Bibliography (A. Claudel), Additions to the Glossary (S. Hotzel); 3 - Internal Wiki Workshop: The RK and M Wiki (P. Maupai), Updating your own country, organisation and regulatory requirement page, General discussion on the wiki; 4 - Strategic Articles: Presentation on Tsunami Stones paper (R. Botez); 5 - Constructing Memory: Verdun 2014 Conference; 6 - Phase-II: Discussion and final approval of Phase-II Proposal (C. Pescatore), Proposal for RWMC collective statement - Flyer on guiding principles, Calendar; 7 - Additional aspects; 8 - Review of Decisions and Closure of the Meeting, Summary of Decision and actions

  7. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan

  8. Specialists' meeting on maintenance and repair of LMFBR steam generators. Summary report

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of the meeting was to review and discuss the experience accumulated in various countries on the general design philosophy of LMFBR steam generators from the view point of maintenance and repair, in-service inspection of steam generator tube bundles, identification and inspection of failed tubes and the cleaning and repairing of failed steam generators. The following main topic areas were discussed by participants: National review presentations on maintenance and repair of LMFBR steam generators - design philosophy for maintenance and repair; Research and Development work on maintenance and repair; Experience on steam generator maintenance and repair. During the meeting papers were presented by the participants on behalf of their countries and organizations. A final discussion session was held and summaries, general conclusions and recommendations were approved by consensus

  9. AER Working Group D on VVER safety analysis - report of the 2009 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2009-01-01

    The AER Working Group D on VVER reactor safety analysis held its 18-th meeting in Rez, Czech Republic, during the period 18-19 May, 2009. The meeting was hosted by the Nuclear Research Institute Rez. Altogether 17 participants attended the meeting of the working group D, 16 from AER member organizations and 1 guest from a non-member organization. The co-ordinator of the working group, S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics: 1) Code validation and benchmarking; 2) Safety analysis and code developments; 3) Reactor pressure vessel thermal hydraulics; 4) Future activities including discussion on the participation in the OECD/NEA Benchmark for the Kalinin-3 NPP

  10. Eighth meeting of the International Working Group on Gas-Cooled Reactors, Vienna, 30 January - 1 February 1989. Summary report. Part 1

    International Nuclear Information System (INIS)

    1989-12-01

    The Eighth Meeting of the IAEA International Working Group on Gas-Cooled Reactors was held in Vienna, Austria, from 30 January - 1 February, 1989. The Summary Report (Part I) contains the Minutes of the Meeting

  11. IAEA consultants` meeting on atomic data base and fusion applications interface, Vienna, 9-13 May 1988. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1988-09-01

    The Summary Report of the IAEA Consultants` Meeting on the ``Atomic Data Base and Fusion Applications Interface`` held at the IAEA Headquarters in Vienna on May 9-13, 1988, is provided. The Report contains a brief review of the meeting proceedings, and the reports of the Working Groups on the A and M dictionary (labelling/indexing system) and on the data storage and exchange system. The conclusions and recommendations of the meeting are also summarized. (author). Figs and tabs.

  12. Summary report of the second research co-ordination meeting on measurement, calculation and evaluation of photon production data

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1996-12-01

    The present report contains the summary of the Second Research Co-ordination Meeting on ''Measurement, Calculation and Evaluation of Photon Production Data'', held in Vienna, Austria, from 21 to 24 May 1996. Summarized are conclusions and recommendations of the meeting together with a detailed list of actions and deadlines, including procedures to prepare the final document of the project. Attached is the agenda of the meeting, list of participants and extended abstracts of their presentations. (author). Refs, figs, tabs

  13. 2011 Annual Meeting of the Safety Pharmacology Society: an overview.

    Science.gov (United States)

    Cavero, Icilio

    2012-03-01

    The keynote address of 2011 Annual Meeting of the Safety Pharmacology Society examined the known and the still to be known on drug-induced nephrotoxicity. The nominee of the Distinguished Service Award Lecture gave an account of his career achievements particularly on the domain of chronically instrumented animals for assessing cardiovascular safety. The value of Safety Pharmacology resides in the benefits delivered to Pharma organizations, regulators, payers and patients. Meticulous due diligence concerning compliance of Safety Pharmacology studies to best practices is an effective means to ensure that equally stringent safety criteria are applied to both in-licensed and in-house compounds. Innovative technologies of great potential for Safety Pharmacology presented at the meeting are organs on chips (lung, heart, intestine) displaying mechanical and biochemical features of native organs, electrical field potential (MEA) or impedance (xCELLigence Cardio) measurements in human induced pluripotent stem cell-derived cardiomyocytes for unveiling cardiac electrophysiological and mechanical liabilities, functional human airway epithelium (MucilAir™) preparations with unique 1-year shelf-life for acute and chronic in vitro evaluation of drug efficacy and toxicity. Custom-designed in silico and in vitro assay platforms defining the receptorome space occupied by chemical entities facilitate, throughout the drug discovery phase, the selection of candidates with optimized safety profile on organ function. These approaches can now be complemented by advanced computational analysis allowing the identification of compounds with receptorome, or clinically adverse effect profiles, similar to those of the drug candidate under scrutiny for extending the safety assessment to potential liability targets not captured by classical approaches. Nonclinical data supporting safety can be quite reassuring for drugs with a discovered signal of risk. However, for marketing authorization

  14. 1986 international meeting of nuclear reactor safety committees

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1987-01-01

    During the week of Oct. 20-23, 1986, nuclear power-plant safety representatives from the Federal Republic of Germany (FRG), France, Japan, and the US assembled to discuss subjects of mutual interest. The meeting, the first of its kind, was organized under the leadership and direction of David A. Ward, Chairman, Advisory Committee on Reactor Safeguards, US Nuclear Regulatory Commission (NRC), and held at the Wingspread Conference Center of the Johnson Foundation in Racine, Wis. Approximately 40 representatives of the several countries attended. Discussions were candid and provided the participants an opportunity to share thoughts and information on nuclear safety concerns and solutions

  15. Nuclear data for the production of therapeutic radionuclides. Summary report of third research coordination meeting

    International Nuclear Information System (INIS)

    Sublet, J.-Ch.; Capote Noy, R.

    2006-08-01

    A summary is given of the Third Research Coordination Meeting on Nuclear Data for the Production of Therapeutic Radionuclides. The new library of evaluated cross-section will cover reactor and accelerator production of therapeutic radionuclides to appropriate specific activities and purity, along with the relevant decay data. A few new reactions were added at this meeting. Technical discussions and the resulting work plan to conclude the data evaluation activities are summarized for every reaction path. Timescales and agreed actions to deliver the database and Technical Report are also given. (author)

  16. 33 CFR 96.240 - What functional requirements must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... a safety management system meet? 96.240 Section 96.240 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.240 What functional...

  17. 77 FR 65000 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-10-24

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide... Use (ETASU) before CDER's Drug Safety and Risk Management Advisory Committee (DSaRM). The Agency plans...

  18. 78 FR 30929 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2013-05-23

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide... (REMS) with elements to assure safe use (ETASU) before its Drug Safety and Risk Management Advisory...

  19. IAEA meeting report of the consultants' meeting on safety improvements of WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1998-05-01

    In 1992 the identification and ranking of safety issues for WWER-440/230 NPPs were completed. Some 100 safety issues have been identified and ranked according to their safety impact on the plant's defence in depth. The IAEA work was based on a conceptual design review and a series of safety review missions to each one of the four sites (Bohunice, Kozloduy, Novovoronezh and Kola) where WWER-440/230 NPPs were in operation. Results were published by the IAEA in February and May 1992. Since the initial publications the IAEA has continued its activities and conducted a number of follow-up missions and technical visits to the NPP sites to review the status of implementation of safety upgradings. In September of 1994 a Consultants Meeting (CM) was held in Vienna to consolidate all the information available to the AEA. The results of that meeting were included in the report WWER-SC-107. During 1995-1997 further information became available from technical visits conducted by the IAEA at the four sites. Therefore, in February 1998 the IAEA convened a CM in Vienna to prepare an up-to-date report on the status of safety improvements at WWER-440/230 NPPs. This report contains the results of that meeting. It reviews the status of remedial actions implemented at each plant in response to the safety issues originally identified in the IAEA reports and the remaining safety concerns. For convenience the issues are presented under broad titles related to: integrity of barriers (Section 2); performance of basic functions (Section 3); performance of supporting functions (Section 4); internal hazards (Section 5); external hazards (Section 6); accident analysis (Section 7); operational functions (Section 8); Section 9 provides an overview of the results of PSA studies performed and under way. Section 10 provides specific information on the status of Armenia NPP. It is presented separately because the IAEA assistance to this plant was provided in the framework of the national technical co

  20. Results of the 3rd Review Meeting of the Convention on Nuclear Safety and Preparatory Works for the 4th Meeting

    International Nuclear Information System (INIS)

    Choi, Young Sung; Choi, Kwang Sik; Kim, Woong Sik

    2006-01-01

    The 3 rd Review Meeting of the Convention on Nuclear Safety (CNS) took place from April 11-22, 2005. Fifty out of fifty-five Contracting Parties (CPs) participated with over 500 delegates in attendance. It was concluded that all CPs in attendance were in compliance with the requirements of the CNS. It was also noted that although the focus tends to be on the triennial national reports and review meetings, the CNS should emphasize an ongoing process that continually promotes the advancement of nuclear safety. With regard to this continuity process, the President of the 3 rd Review Meeting sent to all the CPs a message to remind of the lessons offered and learned from the Meeting and to put them into action as well. The president also asked that the CPs start in earnest later this year their preparations for the Forth Meeting in 2008. This paper introduces the results of the 3 rd Review Meeting and presents some suggestions on preparatory works that should be done for the next Review Meeting

  1. Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

  2. 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.

  3. 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

  4. Summary report from 1. research coordination meeting on nuclear data libraries for advance systems - fusion devices (FENDL - 3)

    International Nuclear Information System (INIS)

    Trkov, A.; Forrest, R.; Mengoni, A.

    2009-03-01

    The first Research Co-ordination Meeting of the Nuclear Data Libraries for Advance Systems - Fusion Devices (FENDL - 3) was held at the IAEA Headquarters in Vienna from 2 to 5 December 2008. A summary of the meeting is given in this report along with discussions which took place. An important outcome of the meeting was the agreement to create a new FENDL-3.0 Starter Library. Finally, a list of task assignments was prepared together with the plan for future CRP activities. (author)

  5. IAEA advisory group meeting on: Critical assessment of tritium retention in fusion reactor materials. Summary report

    International Nuclear Information System (INIS)

    Janev, R.K.; Federici, G.; Roth, J.

    1999-07-01

    The proceedings, conclusions and recommendations of the IAEA Advisory Group Meeting on 'Critical Assessment of Tritium Retention in Fusion Reactor Materials', held on June 7-8, 1999 at the IAEA Headquarters in Vienna, Austria, are briefly described. The report contains a summary of the presentations of meeting participants, a review of the data status (availability and needs) for the fusion most relevant bulk and mixed materials, and recommendations to the IAEA regarding its future activity in this data area. (author)

  6. 77 FR 75176 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-12-19

    ...] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug... being rescheduled due to the postponement of the October 29-30, 2012, Drug Safety and Risk Management... Committee: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide...

  7. Summary of meeting on disposal of LET ampersand D HEPA filters

    International Nuclear Information System (INIS)

    1991-01-01

    This report is a compilation of correspondence between Westinghouse Idaho Nuclear Company and the US EPA over a period of time from 1988 to 1992 (most from 1991-92) regarding waste management compliance with EPA regulations. Typical subjects include: compliance with satellite accumulation requirements; usage of ''Sure Shot'' containers in place of aerosol cans; notice of upcoming recyclable battery shipments; disposition of batteries; HEPA filter leach sampling and permit impacts; functional and operation requirements for the spent filter handling system; summary of meeting on disposal of LET and D HEPA filters; solvent substitution database report; and mercury vapor light analytical testing

  8. Summary record of the topical session of 16. Meeting of the IGSC

    International Nuclear Information System (INIS)

    Van Luik, Abe; Smith, Paul

    2014-01-01

    The sixteenth meeting of the Integration Group for the Safety case (IGSC) included a topical session titled: Handling extreme geological events in safety cases during the post-closure phase. The session included nine presentations on the handling of such events by various national programs, questions and answers on each presentation and ended with a general discussion period. The present document summarises the outcome of the meeting. The document is structured as follows: - Section 2 describes the types of extreme geological events discussed in the session and how these are identified, - Section 3 discusses the measures that can be taken to avoid such events and to mitigate their impact on repositories, - Section 4 describes how the likelihood and consequences of events are assessed, - Section 5 address experiences regarding interactions with regulators and other stakeholders, - Section 6 covers remaining issues and planned R and D to address these, and - Section 7 presents a recommendation for possible future collaborative work on this topic

  9. 76 FR 52016 - NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting

    Science.gov (United States)

    2011-08-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-074)] NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space... meeting of the NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel...

  10. 75 FR 17417 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-04-06

    ...] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory... Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee. This meeting was... Drug Safety and Risk Management Advisory Committee would be held on May 12, 2010. On page 10490, in the...

  11. Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL-3). Summary report from the Second Research Coordination Meeting

    International Nuclear Information System (INIS)

    Sawan, Mohamed E.

    2010-06-01

    The second Research Co-ordination Meeting of the Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL - 3) was held at the IAEA Headquarters in Vienna from 23 to 26 March 2010. A summary of the meeting is given in this report along with the discussions which took place. An important outcome of the meeting was the decision to provide ENDF data libraries (FENDL-3/T) by April 2011. Finally, a list of task assignments was prepared together with the plan for future CRP activities. (author)

  12. Outline of Summary Meeting on Nuclear Fusion Research by Grant-in-Aid (1986-1989) by Monbusho

    International Nuclear Information System (INIS)

    Ishino, Shiori; Nakazawa, Masaharu; Iguchi, Tetsuo

    1990-01-01

    The Summary Meeting on Nuclear Fusion Research by Grant-in-Aid (1986∼1989) of Monbusho was held on Jan. 30∼Feb. 1, 1989 at Gakushi-kaikan in Tokyo. About 300 papers were presented on the research activities as well as some special topics. (author)

  13. Summary report of the third research co-ordination meeting on measurement, calculation and evaluation of photon production data

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1998-01-01

    The present report contains the account of the last meeting of the Co-ordinated Research Project on ''Measurement, Calculation and Evaluation of Photon Production Data''. In addition to the summary of the meeting, the overall results achieved under the project in 1994-1997 are summarized, including the list of publications. The status of work on the Final Report of the project is also given. (author)

  14. Summary report of consultants' meeting on nuclear data of charged-particle interactions for medical therapy applications

    International Nuclear Information System (INIS)

    Capote Noy, R.; Vatnitskiy, S.

    2007-01-01

    A summary is given of a Consultants' Meeting assembled to assess the viability of a new IAEA Co-ordinated Research Project (CRP) on Charged-Particle Interaction Data for Radiotherapy. The need for a programme to compile and evaluate charged-particle nuclear data for therapeutic applications was strongly agreed. Both the technical discussions and the expected outcomes of such a project are described, along with detailed recommendations for implementation. The meeting was jointly organized by NAPC/Nuclear Data Section and NAHU/Dosimetry and Medical Radiation Physics Section. (author)

  15. 78 FR 41496 - Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees

    Science.gov (United States)

    2013-07-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0156] Pipeline Safety: Meetings of the Gas and Liquid Pipeline Advisory Committees AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of advisory committee...

  16. 76 FR 65205 - Commercial Fishing Safety Advisory Committee; Meeting

    Science.gov (United States)

    2011-10-20

    ... discuss various issues relating to safety in the commercial fishing industry. This meeting will be open to...), 915 2nd Ave, Seattle, Washington 98174. For information on facilities or services for individuals with...., Monday through Friday, except Federal Holidays. The telephone number is 202-366-9329. Instructions: All...

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  18. Twenty-eighth Meeting of the Working Party on International Nuclear Data Evaluation Co-operation. Summary Record

    International Nuclear Information System (INIS)

    Chadwick, Mark; ); Danon, Yaron; Herman, Mike; ); Dunn, Mike; ); Kahler, Albert Skip; ); Jacqmin, Robert; ); Plompen, Arjan; ); Fukahori, Tokio; ); Harada, Hideo; ); Iwamoto, Osamu; Yokoyama, Kenji; ); Grudzevich, Oleg; ); Ge, Zhigang; Ruan, Xichao; Wu, Haicheng; Koning, Arjan; ); Mills, Robert; ); Mcnabb, Dennis; ); Palmiotti, Giuseppe; ); Noguere, Gilles; ); Leal, Luiz; ); Cabellos, Oscar; )

    2016-01-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. The 28. Meeting of the WPEC was the occasion to review the experimental activities, the evaluation projects and the Status of subgroups. This document is the summary record of the meeting. It presents: 1 - The reports on experimental activities: Experimental nuclear data activities of relevance to the evaluation projects were reviewed. Detailed information about the experimental activities is given in the reports and view-graphs presented at the meeting. 2 - The review of final or near-final subgroup reports. Results and conclusions of completed or near-completed subgroups were discussed. A summary table of all subgroup status is given in Annex 3. 3 - The status of ongoing subgroups. Activities of ongoing subgroups were presented. A summary table of all subgroup status is given in Annex 3. 4 - The proposals for new subgroups. The subgroup proposal was reviewed by WPEC. Detailed information about this proposal is given in the document. 5 - The forthcoming meetings of interest. The documents presented at the twenty-eight WPEC meeting are presented in the annex 2: Annex 2.1 Working Party on International Nuclear Data Evaluation Co-operation - WPEC; Annex 2.2 WPEC Long-term mandate (updated and extended) on a 'Expert Group on the High Priority Request

  19. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    International Nuclear Information System (INIS)

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX

  20. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX.

  1. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  2. 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

  3. Summary Report of Consultants' Meeting on Beta-Delayed Neutron Emission Evaluation

    International Nuclear Information System (INIS)

    Abriola, Daniel; Singh, Balraj; Dillmann, Iris

    2011-12-01

    A summary is given of a Consultants' Meeting assembled to assess the viability of a new IAEA Co-ordinated Research Project (CRP) on Beta-delayed neutron emission evaluation. The current status of the field was reviewed, cases in which new measurements are needed were identified and the current theoretical models were examined. The best known cases were selected as standards and were assessed and preliminary best values of the emission probabilities were obtained. The need of such a CRP was strongly agreed. Both the technical discussions and the expected outcome of such a project are described, along with detailed recommendations for its implementation. (author)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  5. 1st IAEA research coordination meeting on tritium retention in fusion reactor plasma facing components. October 5-6, 1995, Vienna, Austria. Summary report

    International Nuclear Information System (INIS)

    Langley, R.A.

    1995-12-01

    The proceedings and results of the 1st IAEA research Coordination Meeting on ''Tritium Retention in Fusion Reactor Plasma Facing Components'' held on October 5 and 6, 1995 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of presentations made by the meeting participants, the results of a data survey and needs assessment for the retention, release and removal of tritium from plasma facing components, a summary of data evaluation, and recommendations regarding future work. (author). 4 tabs

  6. Summary report on first research coordination meeting on heavy charged-particle interaction data for radiotherapy

    International Nuclear Information System (INIS)

    Palmans, H.; Noy, R.C.

    2008-04-01

    A summary is given of the First Research Coordination Meeting on Heavy Charged-Particle Interaction Data for Radiotherapy. A programme to compile and evaluate charged-particle nuclear data for therapeutic applications was proposed. Detailed coordinated research proposals were also agreed. Technical discussions and the resulting work plan of the Coordinated Research Project are summarized, along with actions and deadlines. (author)

  7. Workshop on tritium safety and environmental effects, October 15--17, 1990, Aiken, South Carolina: Session summaries

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.

    1991-01-01

    A meeting was held on October 15, 16, 17, 1990 to discuss the state of tritium safety and environmental effects. The meeting was organized with the help of the International Energy Agency planning committee consisting of K. Steinmetz, Y. Seki, G. Nardella, and G. Vivian. Representative of tritium production facilities and heavy water reactor power production were also involved. The meeting was organized to address seven topics in tritium safety that were thought to require further work. The topics were: (1) materials science, (2) environmental models, (3) environmental model validation, (4) tritiated organic compounds, (5) human dosimetry, (6) tritium sampling and measurement, and (7) long-term environmental databases

  8. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

    GARVIN, L. J.; JENSEN, M. A.

    2004-04-13

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  9. 76 FR 63929 - Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and...

    Science.gov (United States)

    2011-10-14

    ...] Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and... Administration (FDA). The meeting will be open to the public. Name of Committees: Drug Safety and Risk Management... Safe Use (ETASU) before its Drug Safety and Risk Management Advisory Committee (DSaRM). On December 1...

  10. Summary of ORNL work on NRC-sponsored HTGR safety research, July 1974-September 1980

    International Nuclear Information System (INIS)

    Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Delene, J.G.; Harrington, R.M.; Hatta, M.; Hedrick, R.A.; Johnson, L.G.; Sanders, J.P.

    1982-03-01

    A summary is presented of the major accomplishments of the Oak Ridge National Laboratory (ORNL) research program on High-Temperature Gas-Cooled Reactor (HTGR) safety. This report is intended to help the nuclear Regulatory Commission establish goals for future research by comparing the status of the work here (as well as at other laboratories) with the perceived safety needs of the large HTGR. The ORNL program includes extensive work on dynamics-related safety code development, use of codes for studying postulated accident sequences, and use of experimental data for code verification. Cooperative efforts with other programs are also described. Suggestions for near-term and long-term research are presented

  11. Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Rafferty, Barbara

    2002-01-01

    The Second Review Meeting of the Contracting Parties to the Convention on Nuclear Safety was held in the Headquarters of the International Atomic Energy Agency in Vienna from 15-26 April 2002, under the chairmanship of the President, Mr Miroslav Gregoric, Director of the Slovenian Nuclear Safety Authority. The Convention on Nuclear Safety entered into force in October 1996, has been signed by sixty-five States and ratified by fifty-four, bringing within its scope 428 of the 448 nuclear reactors worldwide. The Convention aims to achieve and maintain a high level of nuclear safety worldwide, through inter alia enhancement of national measures and international co-operation. Obligations on Contracting Parties in accordance with the Convention include: the establishment and maintenance of a legislative and regulatory framework to govern the safety of land-based civil nuclear installations; the allocation of adequate financial and human resources to support the safety objectives; ensuring that all reasonably practicable improvements to safety are made as a matter of urgency. Adherence to this Convention entails two basic commitments by each Contracting Party: to prepare and make available a national report for review; and to subject its national report to a peer review by the other Contracting Parties. Thus, being a Contracting Party to this Convention involves: including in the national report a self-assessment of steps and measures already taken and in progress to implement the Convention obligations; taking an active part in an open and transparent review of its national report and the Reports of other Contracting Parties; and a commitment to a continuous learning and improving process, something which is a key element of a strong safety culture. The peer review of national reports takes place every three years, the first having been held in 1999. The Second Review Meeting was attended by delegates from 46 contracting parties. During the review certain issues were

  12. 77 FR 26790 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2012-05-07

    ... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Bureau of Justice... meeting (via conference call-in) of the Public Safety Officer Medal of Valor Review Board (``Board'') to... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions...

  13. 2nd (final) IAEA research co-ordination meeting on 'plasma-material interaction data for mixed plasma facing materials in fusion reactors'. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2001-11-01

    The proceedings and conclusions of the 2nd Research Co-ordination Meeting on 'Plasma-Material Interaction Data for Mixed Plasma Facing Materials in Fusion Reactors', held on October 16 and 17, 2000 at the IAEA Headquarters in Vienna, are briefly described. This report includes a summary of the presentations made by the meeting participants and a review of the accomplishments of the Co-ordinated Research Project (CRP). In addition, short summaries from the participants are included indicating the specific research completed in support of this CRP. (author)

  14. Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-11-01

    The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX.

  15. Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III

    International Nuclear Information System (INIS)

    1977-11-01

    The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX

  16. Summary report of the 1. research co-ordination meeting on compilation and evaluation of photonuclear data for applications

    International Nuclear Information System (INIS)

    1997-04-01

    The present report contains the summary of the first Research Co-ordination Meeting on ''Compilation and Evaluation of Photonuclear Data for Applications'', held in Obninsk, Russia, from 3 to 6 December 1996. The project aims to produce a Technical Document on Photonuclear Data Library for Applications and to develop an IAEA Photonuclear Data Library. Summarized are the conclusions and recommendations of the meeting together with a detailed list of actions. Attached is the information sheet on the project, the agenda of the meeting and the list of participants along with extended abstracts of their presentations. Refs, figs, tabs

  17. 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)

  18. 75 FR 23782 - Drug Safety and Risk Management Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2010-05-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug...: Drug Safety and Risk Management Advisory Committee. General Function of the Committee: To provide...

  19. High committee for nuclear safety transparency and information. March 17, 2009 meeting

    International Nuclear Information System (INIS)

    2009-03-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 9 main topics: 1 - presentation by the French nuclear safety authority (ASN) of a dismantling strategy for nuclear facilities, in particular taking into account a final state for the site and the information of populations; 2 - status of the next campaign of iodine tablets distribution; 3 - the management of ancient uranium mines and in particular the long-term environmental and health impact of mine tailings; 4 - the implementation of the high committee's recommendations; 5 - work progress of the working group on information transparency; 6 - Areva's invitation of the working group on information transparency to assist to the organisation of a Mox fuel convoy between Cherbourg and Japan; 7 - progress of the working group on the elaboration of a 'communication scale' comparable to the INES scale; 8 - presentation of the meetings organized by the ANCLI (French national association of local information commissions) about the implementation of the Aarhus convention; 9 - presentation by the IRSN (Institute of radiation protection and nuclear safety) of its communication approach towards the public. (J.S.)

  20. The U.S. Nuclear Data Network: Summary of the twentieth meeting

    International Nuclear Information System (INIS)

    1994-01-01

    Topics discussed at this meeting were: assessment of the nuclear data program from the perspective of the funding agency; status of high spin evaluations for ENSDF; recommendation for name change of master file from Nuclear Structure Reference to Nuclear Science Reference; status of ENSDF, Table of Isotopes, VuENSDF, on-line system at the NNDC, and Nuclear Data Sheets; summary of the discussion of the Formats and Procedures Subcommittee; long range plan for nuclear structure data; a description of methods of optimization of nuclear structure evaluations and how to evolve this activity into the forefront of research such as high-spin physics; code development which includes improvements in the databases and evaluator tools; and future means of data dissemination

  1. Interim summary report of the safety case 2009

    International Nuclear Information System (INIS)

    2010-03-01

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. The present Interim Summary Report represents a major contribution to the development of this safety case. The report has been compiled in accordance with Posiva's current plan for preparing this safety case. A full safety case for the KBS-3V variant will be developed to support the Preliminary Safety Assessment Report (PSAR) in 2012. The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository. Current understanding of the evolution of the disposal system indicates that, except a few unlikely circumstances affecting a small number of canisters, spent fuel will remain isolated, and the radionuclides contained within the canisters, for hundreds of thousands of years or more, in accordance with the base scenario. Confidence in this base scenario derives, in the first place, from the

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

    International Nuclear Information System (INIS)

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

    2007-09-01

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

  3. Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA advisory group meeting

    Energy Technology Data Exchange (ETDEWEB)

    Pronyaev, V G

    2001-02-01

    The IAEA Nuclear Data Section convened the fourteenth meeting of the International Nuclear Structure and Decay Data Evaluators Network at IAEA Headquarters, Vienna, 4-7 December 2000. The meeting was attended by 22 scientists from 7 Member States and 1 international organization concerned with compilation, evaluation, and dissemination of nuclear structure and decay data. The present document contains a meeting summary, the recommendations, the data center reports and proposals considered by the participants. (author)

  4. Eighth meeting of the International Working Group on Gas-Cooled Reactors Vienna, 30 January - 1 February 1989. Summary report. Part 2

    International Nuclear Information System (INIS)

    1989-12-01

    The Eighth Meeting of the IAEA International Working Group on Gas-Cooled Reactors was held in Vienna, Austria, from 30 January - 1 February, 1989. The Summary Report (Part II) contains the papers which review the national programmes in the field of Gas-Cooled Reactors and other presentations at the Meeting. Refs, figs and tabs

  5. Summary of Needs and Opportunities from the 2011 Residential Energy Efficiency Stakeholders Meeting: Atlanta, Georgia -- March 16-18, 2011

    Energy Technology Data Exchange (ETDEWEB)

    2011-05-01

    This summary report outlines needs and issues for increasing energy efficiency of new and existing U.S homes, as identified at the U.S Department of Energy Building America program Spring 2011 stakeholder meeting in Atlanta, Georgia.

  6. EPR meets the next generation PWR safety requirements

    International Nuclear Information System (INIS)

    Bouteille, Francois; Czech, Juergen; Sloan, Sandra

    2006-01-01

    At the origin was the common decision in 1989 of Framatome and Siemens to cooperate to design a Nuclear Island which meets the future needs of utilities. EDF and a group of main German Utilities joined this effort in 1991 and from that point were completely involved in the progress of the work. Compliance of the EPR with the European Utility Requirements (EUR) was verified to ensure a large acceptability of the design by other participating utilities. In addition, the entire process was backed up to the end of 1998 by the French and the German Safety Authorities which engaged into a long-lasting cooperation to define common requirements applicable to future Nuclear Power Plants. Upon signature of the Olkiluoto 3 contract, STUK, the Finnish safety and radiation authority, began reviewing the design of the EPR. Upon the favorable recommendation of STUK, the Finnish government delivered a Construction License for the Olkiluoto 3 NPP on February 17, 2005. Following the positive conclusion of the political debate in France with regard to nuclear energy, EDF will also submit a request to start the construction of an EPR on the Flamanville site. In the US, the first steps in view of a Design Certification by the NRC have been taken. These three independent decisions make the EPR the leading first generation 3+ design under construction. Important safety functions are assured by separate systems in a straightforward operating mode. Four separate, redundant trains for all safety systems are installed in four separate layout division for which a strict separation is ensured so that common mode failure, for example due to internal hazards, can be ruled out. A reduction in common mode failure potential is also obtained by design rules ensuring the systematic application of functional diversity. A four train-redundancy for the major safety systems provides flexibility in adapting the design to maintenance requirements, thus contributing to reduce the outage duration. Additional

  7. 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

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

    International Nuclear Information System (INIS)

    Abriola, D.; Tuli, J.K.

    2009-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-09-15

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

  10. 29 CFR 1905.41 - Summary decision.

    Science.gov (United States)

    2010-07-01

    ... OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 Summary Decisions § 1905.41 Summary decision. (a) No genuine issue... 29 Labor 5 2010-07-01 2010-07-01 false Summary decision. 1905.41 Section 1905.41 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RULES OF...

  11. Co-ordination of the international network of nuclear structure and decay data evaluators. Summary report of an IAEA advisory group meeting

    International Nuclear Information System (INIS)

    Pronyaev, V.G.

    1999-03-01

    The IAEA Nuclear Data Section convened the thirteenth meeting of the International Nuclear Structure and Decay Data Evaluators Network at the IAEA Headquarters, Vienna, 14-17 December 1998. The meeting was attended by 30 scientists from 10 Member States and 2 international organizations concerned with compilation, evaluation, and dissemination of nuclear structure and decay data. The present document contains a meeting summary, the conclusions and recommendations, the data center reports and proposals considered by the participants. (author)

  12. Summary of the BioLINK SIG 2013 meeting at ISMB/ECCB 2013.

    Science.gov (United States)

    Verspoor, Karin; Shatkay, Hagit; Hirschman, Lynette; Blaschke, Christian; Valencia, Alfonso

    2015-01-15

    The ISMB Special Interest Group on Linking Literature, Information and Knowledge for Biology (BioLINK) organized a one-day workshop at ISMB/ECCB 2013 in Berlin, Germany. The theme of the workshop was 'Roles for text mining in biomedical knowledge discovery and translational medicine'. This summary reviews the outcomes of the workshop. Meeting themes included concept annotation methods and applications, extraction of biological relationships and the use of text-mined data for biological data analysis. All articles are available at http://biolinksig.org/proceedings-online/. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  13. Proceedings of 2nd PHWR operating safety experience meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage.

  14. Proceedings of 2nd PHWR operating safety experience meeting

    International Nuclear Information System (INIS)

    1991-04-01

    Papers presented during the eight sessions of the meeting were devoted to the impact of PHWR operating experience on design of civil structures (reactor building integrity); operating experiences related to pressure tubes, nuclear steam supply system, plant stability; reactor maintenance and control systems, reactor operational safety. Some events concerned with reactor shutdown due to power failures are described, as well as action undertaken to prevent major damage

  15. CSNI Status summary on utilization of best-estimate methodology in safety analysis and licensing

    International Nuclear Information System (INIS)

    1996-10-01

    The PWG 2 Task Group on Thermal Hydraulic System Behavior has discussed the subject of the use of best-estimate codes in the licensing process (codes that model thermal hydraulic processes are important to assessing safety system performance). The Task Group set out to determine the prevailing practices in member countries, concerning safety assessment and safety review of transients affecting the reactor coolant system. A summary of information provided by member countries in response to eleven questions is given: Who is Responsible for Safety Analysis? Who is Responsible for Review and Evaluation of Safety Analysis? Do the Regulations Permit the use of Best-Estimate Codes? What are the Requirements for What Constitutes a Best Estimate Code? What are the Requirements Concerning Code Documentation? What are the Requirements for Review of Code Models and Correlations? What are the Requirements Concerning Code Assessment? What are the Requirements Concerning Initial and Boundary Conditions? What are the Requirements Concerning Operability of Active Equipment? What are the Requirements Concerning Operator Actions?

  16. Summary Report of the First Research Coordination Meeting on Primary Radiation Damage Cross Sections

    International Nuclear Information System (INIS)

    Stoller, R.E.; Greenwood, L.R.; Simakov, S.P.

    2013-12-01

    The Nuclear Data Section of IAEA has initiated a new Coordinated Research Project with the main goal of reviewing and recommending primary damage response functions for neutron and ion irradiations of materials. The output of this CRP will be a database of recommended damage response functions for selected materials with corresponding documentation. It will serve the needs of the fission, fusion and accelerator neutron source communities. The first Research Coordination Meeting (RCM) was held 4 to 8 November 2013 at the IAEA. At this meeting, the attendees discussed the objectives of the whole CRP, presented their contributions and elaborated on consolidated recommendations and actions for implementation over the next 1.5 year period. This Summary Report documents the individual contributions and joint decisions made during this meeting. The identified research needs were refined through extensive discussion, and a consensus was developed which defined the CRP objectives in two broad categories. The first addresses the underlying physics-related research relevant to nuclear reactions and ion stopping powers, while the second task will address the development of new materials damage response functions. (author)

  17. Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL 3.0). Summary report of the Third Research Coordination Meeting

    International Nuclear Information System (INIS)

    Sawan, Mohamed E.

    2012-03-01

    The third Research Co-ordination Meeting of the Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL-3) was held at IAEA Headquarters in Vienna from 6 to 9 December 2011. A summary of the presentations given during meeting is given in this report along with the discussions that took place. A list of actions necessary to complete the library production, processing and testing are given. Details of the documents arising from the CRP were agreed. (author)

  18. Summary of FY 1997 work related to JAPC-U.S. DOE contract study on improvement of core safety - study on GEM (III)

    International Nuclear Information System (INIS)

    Burke, T.M.

    1998-01-01

    FFTF was originally designed/constructed/operated to develop LMFBR fuels and materials. Inherent safety became a major focus of the US nuclear industry in the mid 1980's. The inherent safety characteristics of LMFBRs were recognized but additional enhancement was desired. The presentation contents are: Fast Flux Test Facility history and status; Overview of contract activities; Summary of loss of flow without scram with GEMs testing; and Summary of pump start with GEMs testing

  19. Summary report of third research coordination meeting on updated decay data library for actinides

    International Nuclear Information System (INIS)

    Kellett, M.A.

    2009-07-01

    The third meeting of the Coordinated Research Project on 'Updated Decay Data Library for Actinides' was held at the IAEA, Vienna on 8-10 October 2008. A summary of the presentations made by each participant is given, along with subsequent discussions. The evaluation procedure was reviewed, and a short tutorial session was given on the use of software adopted from the Decay Data Evaluation Project (DDEP). The list of radionuclides under review and evaluation was updated, along with their agreed allocation amongst participants. (author)

  20. Report of the 52. meeting of the Superior Council of the Nuclear Safety and Information (project)

    International Nuclear Information System (INIS)

    2000-01-01

    Since june 2000, the CSSIN (Superior Council on Nuclear Safety and Information) decided to present the meeting of its sessions, on the Internet site of the Nuclear Safety Authority. This document is the meeting project concerning the session of the 27 june 2000. The following subjects have been treated: the Blayais accident and its consequences; the Euratom Directive transposition on the workers and people protection; methodology and organization of the CSSIN concerning the civil nuclear installations and the radiation protection; actualization of the CSSIN heading in the Internet site of the Nuclear Safety Authority. (A.L.B.)

  1. High committee for nuclear safety transparency and information. December 18, 2008 meeting

    International Nuclear Information System (INIS)

    2008-12-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main topics: 1 - a presentation of nuclear medicine by Prof. Devaux, of its domains of application and the respect of radiation protection rules; 2 - the launching of a working group on the transparency/secrecy problem with nuclear activities; 3 - the elaboration of an environmental radioactivity index by the nuclear safety authority (ASN); 4 - the order addressed to the Cruas nuclear facility for the lack of standardized marking and maintenance of pipes used for the transport of explosive fluids; 5 - the consequences of the blocking of 2 fuel assemblies (out of 157) in the Tricastin reactor core; 6 - the flood at the Tricastin site, its origin and consequences. (J.S.)

  2. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 2, presents papers on: Severe accident research; Severe accident and policy implementation; and Accident management. The individual papers have been cataloged separately

  3. Specialized meeting on 'Current topics of reactor safety research in Germany'

    International Nuclear Information System (INIS)

    Kruessenberg, Anne

    2013-01-01

    On October 11 and 12, 2012, the 2-day specialized meeting organized by the Thermodynamics and Fluid Dynamics Group together with the Dresden-Rossendorf Helmholtz Center and TUeV NORD SysTec GmbH and Co.KG was held at the Dresden-Rossendorf Helmholtz Center within the series of events on 'Current Topics of Safety Research in Germany.' The program of lectures was supplemented by poster presentations and exhibitions by the members of the joint research groups and companies working in the fields. The meeting again was very well attended by over 100 persons. (orig.)

  4. Summary of a meeting on non-electrical energy extraction from fusion reactors at AEC Germantown Headquarters, March 20, 1973

    International Nuclear Information System (INIS)

    Miley, G.H.

    1973-01-01

    The following six topics were discussed at the meeting: (1) energy forms available from the plasma, (2) materials processing, (3) hydrogen production, (4) plasma chemistry/radiation processing, (5) coherent radiation/broad-band radiation, and (6) neutron applications. Summaries are given for each topic. (U.S.)

  5. High committee for nuclear safety transparency and information. July 1, 2009 meeting

    International Nuclear Information System (INIS)

    2009-07-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 5 main points: 1 - radioactive waste management: status and steps of the June 28, 2006 law, ANDRA's projects of deep geologic disposal for long living/high-medium activity wastes and of low depth disposal for long living/low activity wastes, French nuclear safety authority (ASN) opinion about the sites choice, implementation of article 10 of the June 28, 2006 law relative to public information; 2 - progress of the working groups' works on transparency and secrecy, on the development of a communication scale, and on the creation of an Internet portal for the radio-ecological follow-up of nuclear sites; 3 - comments of the ASN's report on the nuclear safety and radiation protection in France in 2008; 4 - procedure of management of the radio-physicists shortage in order to warrant the patients' safety and information; 5 - miscellaneous points: project of European directive on nuclear safety, organisation of a visit day onboard of a ship for nuclear materials transportation, comments about the by-law from May 5, 2009, relative to the exemption to informing consumers about the addition of radionuclides to consumption and construction products. (J.S.)

  6. IAEA consultants' meeting on selection of basic evaluations for the FENDL-2 library. Summary report

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1996-09-01

    FENDL-1 is the international reference nuclear data library for fusion design applications, available from the IAEA Nuclear Data Section. FENDL/E is the sublibrary for evaluated neutron reaction data. An updated version, FENDL-2, is being developed. The present report contains the Summary of the IAEA Consultants' Meeting on ''Selection of Basic Evaluations for the FENDL-2 Library'', held at Karlsruhe, Germany, from 24 to 28 June 1996. This meeting was organized by the IAEA Nuclear Data Section (NDS) with the co-operation and assistance of local organizers of the Forschungszentrum Karlsruhe, Germany. Summarized are the conclusions and recommendations for the selection of basic evaluations from candidates submitted by five national projects (JENDL-FF, BROND, EFF, ENDF/B-VI and CENDL) for FENDL/E-2.0 international reference data library. (author). 1 tab

  7. Hanford Site Environment Safety and Health (ES and H) FY 1999 and FY 2000 Execution Commitment Summary

    Energy Technology Data Exchange (ETDEWEB)

    REEP, I.E.

    1999-12-01

    All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the S&H resources that support these activities. The fiscal year (FY) 1999 and 2000 information (Sieracki 1999) and data contained in the ''Hanford Site Environment, Safety and Health Fiscal Year 2001 Budget-Risk Management Summary'' (RL 1999) were the basis for preparing this report. Fiscal year 2000 finding of Office of Environmental Management (EM) and Office of Nuclear Energy, Science and Technology (NE) activities is based on the President's budget of $1,065.1 million and $28.0 million, plus $2.7 million carryover finding, respectively, as of October 31, 1999. Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2002 ES&H Budget-Risk Management Summary to be issued in May 2000. This report provides the end-of-year status of FY 1999 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2000 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H ''Guidance for FY200l Budget Formulations and Execution'' (DOE 1999).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-10-15

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

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

    2011-10-01

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

  10. 78 FR 70623 - Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory...

    Science.gov (United States)

    2013-11-26

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2009-0203] Pipeline Safety: Meeting of the Gas Pipeline Advisory Committee and the Liquid Pipeline Advisory Committee AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. [[Page...

  11. Meetings of all the contracting parties of agreements on Nuclear Safety of the IAEA

    International Nuclear Information System (INIS)

    Ripoll Carulla, S.

    2003-01-01

    One of the most original aspects at the Convention on Nuclear Safety was the incorporation of the mechanism for Meetings with Contracting States into Chapter III. This mechanism has become one of the most characteristic elements at the convention, which is usually defined as a motivational convention, due in large part to the actual existence of these meetings. (Author)

  12. Chairman’s Summary [International Experts’ Meeting on Reactor and Spent Fuel Safety in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant, Vienna (Austria), 19-22 March 2012

    International Nuclear Information System (INIS)

    Meserve, R.A.

    2012-01-01

    General remarks In furtherance of the IAEA Action Plan on Nuclear Safety (the Action Plan) unanimously endorsed by the Member States as a result of the accident at the Fukushima Daiichi nuclear power plant, the IAEA held an International Experts’ Meeting (“IEM”) from 19-22 March 2012. The primary objectives of this IEM were to analyze relevant technical aspects of reactor and spent nuclear fuel management safety and performance; to review what is known to date about the accident in order to understand more fully its root causes; and to share the lessons learned from the accident. These objectives served to pursue several purposes of the Action Plan: · to discuss the results of Member States national assessments of the safety vulnerabilities of nuclear power plants in light of lessons learned to date (Action Plan, Safety Assessments in the Light of the Accident at TEPCO's Fukushima Daiichi Nuclear Power station bullet no. 11); · to analyze all relevant technical aspects and learn the lessons from the Fukushima accident. (Action Plan, Communication and Information Dissemination bullet no. 41); and · to help facilitate and to continue to share with member states a fully transparent assessment of the accident in cooperation with Japan (Action Plan, Communication and Information Dissemination bullet no. 5). The IEM was attended by approximately 230 experts from 44 Member States and 4 international organizations. There were wide-ranging and open discussions and a full exchange of information. This summary is intended to reflect observations that were made at the IEM, but does not necessarily reflect the consensus of the participants. The IEM revealed that the Member States (including regulators, industry, and technical support organizations), the IAEA Secretariat, and other relevant organizations had undertaken very significant efforts to analyze the Fukushima accident and to take appropriate actions to respond to it. The overall efforts have been comprehensive

  13. Summary record of the experts meeting on the proposed OECD-IRSN STLOC project

    International Nuclear Information System (INIS)

    2004-01-01

    The purpose of this meeting was to determine the interest in member countries for the types of LOCA tests envisaged in the STLOC programme proposed by IRSN. The IRSN proposal was circulated among this Group in advance of the meeting. After the presentations and discussions, the Group recommendations were as follows: different views were expressed as to the need to perform the LOCA integral tests; there was an understanding that the results of separate effect tests (ANL, JAERI, Halden) would need to be obtained before deciding on the intended LOCA tests proposed in STLOC; IRSN and the OECD-NEA should explore the possibility to run the first ST test with air ingress (STLOC1), for which partial funding already exists (this test is foreseen for 2008); the need of LOCA tests as envisaged in STLOC should be re-assessed in about three years time (2006); analytical and experimental progress on LOCA tests should be monitored until then, through for instance the SEGFSM. An executive summary of the IRSN Source term LOCA program LOCA part is given in an appendix

  14. Evaluating the horizontal alignment of safety management activities through cross-reference of data from safety audits, meetings and investigations

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2017-01-01

    Vertical and horizontal alignment within organizations are seen as prerequisites for meeting strategic objectives and indications of effective management. In the area of safety management, the concept of vertical alignment has been followed through the introduction of hierarchical structures and

  15. Updating Photonuclear Data Library and Generating a Reference Database for Photon Strength Functions. 1st Research Coordination Meeting. Summary Report

    International Nuclear Information System (INIS)

    Goriely, S.; Dimitriou, P.

    2016-07-01

    A summary is given of the 1 st Research Coordination Meeting of the new IAEA Co-ordinated Research Project (CRP) on Updating the Photonuclear Data Library and Generating a Reference Database for Photon Strength Functions. Participants presented their work, reviewed the current status of the field with regards to measurements, theoretical models and evaluations, discussed the scope of the work to be undertaken and agreed on a list of priorities and task assignments necessary to achieve the goals of the CRP. A summary of the presentations and discussions is presented in this report. (author)

  16. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 3, presents papers on: Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive light water researchers; Thermal Hydraulics; and Earth sciences. The individual papers have been cataloged separately

  17. Meeting summary of the second CSNI specialist meeting on simulators and plant analyzers - Current Issues in Nuclear Power Plant Simulation

    International Nuclear Information System (INIS)

    1998-01-01

    The Second CSNI Specialist Meeting on Simulators and Plant Analyzers: Current Issues in Nuclear Power Plant Simulation was held in Espoo, Finland, from September 29 through October 2, 1997. It was organised by CSNI Principal Working Group on Coolant System Behaviour (PWG2), Task Group on Thermal Hydraulic Applications (TG-THA), in co-operation with Technical Research Centre of Finland. The meeting in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. The previous meeting held in Lappeenranta, Finland, in 1992 collected some 85 participants from 12 countries, presenting a total of 40 papers. The meeting was structured into 6 sessions covering the important aspects of development and use of simulators and plant analyzers: Session I: New objectives, Requirements and Concepts. This session covered the progress experienced since the 1. simulator meeting and tried to address the changing role of simulators based on the changes in users' needs and developing possibilities. Session II: Trends in Simulation Technology. This session was reserved for studying the current trends in the simulation technology: software environments, visualisation, simulator configuration tools, programming languages and computer systems. Session III: Training and human factor studies using simulators. This session was created for studying the status of different uses of simulators such as educational simulators, human factor studies and integrated safety assessment in addition to traditional training. Regarding to the severe accidents, a question was raised whether the simulator use should be for training or education. Session IV: Modelling techniques. The session on modelling techniques was included to cover recent developments in the modelling techniques applicable to training

  18. Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

    International Nuclear Information System (INIS)

    Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

    2004-01-01

    Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

  19. Inventory of Federal energy-related environment and safety research for FY 1978. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1979-12-01

    The FY 1978 Federal Inventory is a compilation of 3225 federally funded energy-related environmental and safety reserch projects. It consists of three volumes: an executive summary providing an overview of the data (Volume I), a catalog listing each Inventory project followed by series of indexes (Volume II), and an interactive terminal guide giving instructions for on-line data retrieval (Volume III). Volume I reviews the inventory data as a whole and also within each of three major categories: biomedical and environmental research, environmental control technology research, and operational safety research

  20. 75 FR 67805 - The Future of Aviation Advisory Committee (FAAC) Subcommittee on Aviation Safety; Notice of Meeting

    Science.gov (United States)

    2010-11-03

    ...-2010-0074] The Future of Aviation Advisory Committee (FAAC) Subcommittee on Aviation Safety; Notice of..., announces a meeting of the FAAC Subcommittee on Aviation Safety, which will be held at the offices [[Page... needs, challenges, and opportunities of the global economy. The Subcommittee on Aviation Safety will...

  1. Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  2. 1st IAEA research co-ordination meeting on 'plasma-material interaction data for mixed plasma facing materials in fusion reactors'. Summary report

    International Nuclear Information System (INIS)

    Janev, R.K.; Longhurst, G.

    1998-12-01

    The proceedings and conclusions of the 1st IAEA Research Co-ordination Meeting on 'Plasma-Material Interaction Data for Mixed Plasma Facing Materials in Fusion Reactors', held on December 19 and 20, 1998 at the IAEA Headquarters in Vienna, are briefly described. This report includes a summary of the presentations made by meeting participants, a review of the data availability and data needs in the areas from the scope of the Co-ordinated Research Project (CRP) on the subject of the meeting, and recommendations regarding the future work within this CRP. (author)

  3. Water Cluster Leaders Meeting Summary Report 2016

    Science.gov (United States)

    As part of its efforts to support environmental technology innovation clusters, U.S. EPA hosted a Water Technology Innovation Cluster Leaders Meeting on September 25, 2016, in New Orleans, Louisiana. The meeting was an opportunity for cluster leaders from across the globe to meet...

  4. High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee

    International Nuclear Information System (INIS)

    2009-11-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache, in relation with

  5. OECD/CSNI specialist meeting on fuel coolant interactions: summary and conclusions

    International Nuclear Information System (INIS)

    1997-01-01

    Research activities and interest on fuel-coolant interaction (FCI) have been increased and broadened since the last CSNI Specialist Meeting held in January 1993. Significant experimental and analytical research has been performed in many OECD countries and others. The growing international interest is, in large part, due to the emphasis on broader aspects of FCI ranging from melt quenching and coolability to energetic explosions (both in- and ex-vessel), and their relevance and applications to next-generation reactor design as well as accident management strategies. The objectives of the meeting are to review the knowledge and to obtain consensus on the phenomenology of FCI and in predicting FCI behavior in LWRs severe accidents; to identify those areas of FCI phenomena and prediction which are important for reactor safety but still poorly understood and require further study with clear methodologies; to inform the community and the regulatory agencies of the status of FCI issues, especially in the application to accident management and future reactor designs. The various sessions are: reactor applications, pre-mixing, propagation / trigger, experiments

  6. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    International Nuclear Information System (INIS)

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  7. Conference summaries

    International Nuclear Information System (INIS)

    1987-01-01

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

  8. 2013 Building America Research Planning Meeting Summary

    Energy Technology Data Exchange (ETDEWEB)

    Metzger, C. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Hunt, S. [Confluence Communications, Missoula, MT (united States)

    2014-02-01

    The Building America Research Planning Meeting was held October 28-30, 2013, in Washington, DC. This meeting provides one opportunity each year for the research teams, national laboratories and Department of Energy (DOE) managers to meet in person to share the most pertinent information and collaboration updates. This report documents the presentations, highlights key program updates, and outlines next steps for the program.

  9. Summary and outlook for KEKTC5

    International Nuclear Information System (INIS)

    Quinn, Helen

    2002-01-01

    This is the summary talk of a meeting held at the KEK, Tsukuba, Japan, November 20-22, 2001. I give a brief summary of the talks we heard, and a few comments of my own on various points that have been made. Other talks given at this meeting are referred to by the speakers last name; these talks will appear in the same proceedings. See these talks for the detailed references for each subject

  10. 2013 Building America Research Planning Meeting Summary

    Energy Technology Data Exchange (ETDEWEB)

    Metzger, Cheryn E. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Hunt, Stacy [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2014-02-01

    The Building America (BA) Research Planning Meeting was held October 28-30, 2013, in Washington, DC. This meeting provides one opportunity each year for the research teams, national laboratories and Department of Energy (DOE) managers to meet in person to share the most pertinent information and collaboration updates. This report documents the presentations, highlights key program updates, and outlines next steps for the program.

  11. Update of X- and γ-ray decay data standards for detector calibration and other applications. Summary report of the 1. research co-ordination meeting

    International Nuclear Information System (INIS)

    Herman, M.; Nichols, A.

    1999-07-01

    The discussions and conclusions of the First Research Co-ordination Meeting to Update X- and γ-ray Decay Data Standards for Detector Calibration are described in this summary report. The agreed list of radionuclides to be evaluated is given, along with the evaluation procedures and assignment of tasks among participants of the CRP. 14 presentations given at the meeting were indexed separately

  12. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

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

  13. Richland Operations (DOE-RL) Environmental Safety Health (ES and H) FY 2000 and FY 2001 Execution Commitment Summary

    Energy Technology Data Exchange (ETDEWEB)

    REEP, I.E.

    2000-12-01

    All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the Safety and Health (S&H) resources that support these activities. The fiscal year (FY) 2000 and 2001 information and data contained in the Richland Operations Environment, Safefy and Health Fiscal Year 2002 Budget-Risk Management Summary (RL 2000a) were the basis for preparing this report. Fiscal year 2001 activities are based on the President's Amended Congressional Budget Request of $689.6 million for funding Ofice of Environmental Management (EM) $44.0 million for Fast Flux Test Facility standby less $7.0 million in anticipated DOE, Headquarters holdbacks for Office of Nuclear Energy, Science and Technology (NE); and $55.3 million for Safeguards and Security (SAS). Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2003 ES&H Budget-Risk Management Summary to be issued in May 2001. This report provides the end-of-year status of FY 2000 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2001 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H guidance contained in the FY 2002 Field Budget Call (DOE 2000).

  14. Trends in safety pharmacology: posters presented at the annual meetings of the Safety Pharmacology Society 2001-2010.

    Science.gov (United States)

    Redfern, William S; Valentin, Jean-Pierre

    2011-01-01

    The inaugural meeting of the Safety Pharmacology Society (SPS) was in 2001, soon after ICH S7A had been adopted. The 10th anniversary is an appropriate milestone at which to analyse trends in the science and themes of safety pharmacology, as reflected in posters presented at the annual meetings. The source information was the poster abstract booklets from each of the first ten annual meetings. The number of posters rose steadily from 34 in 2001 to 201 in 2010. The proportion of posters containing in vitro data has remained constant throughout the decade at ~30%. In terms of organ functions, themes relating to the cardiovascular system (CVS) have always generated the majority of posters, remaining above 60% of the total for the last 9years. The dominant theme has been around 'QT liability'. This peaked in 2003 at 68% of all posters presented, around the time of the ICHS7B discussions, and has remained above 30% thereafter. Apart from 2003 (dipping to 4%), CNS-related posters have remained steady at 11-17% throughout the decade. Respiratory-related posters have remained at 5-8% over the last 5years. Gastrointestinal (GI)-related posters have contributed 2-6% throughout the decade, and renal-related posters 1-3%. Posters on combined organ assessments have appeared in recent years. The relative emphasis on the different organ functions is broadly proportional to the causes of candidate drug attrition preclinically, whereas both CNS and GI are under-represented when considering their contribution to significant adverse effects during clinical development. Trends are either regulatory-driven (e.g. increase in posters on abuse-dependence liability since EMEA/CHMP/SWP/94227/2004), technology-driven (e.g. automated hERG assay; left ventricular function; non-invasive CVS measurements; stem cells, etc.), or relate to the predictive ability of safety pharmacology data (e.g. clinical translation initiatives; concordance between in vitro and in vivo preclinical data; integrated

  15. Landsat Science Team: 2017 Winter Meeting Summary

    Science.gov (United States)

    Schroeder, Todd A.; Loveland, Thomas; Wulder, Michael A.; Irons, James R.

    2017-01-01

    The summer meeting of the joint U.S. Geological Survey (USGS)-NASA Landsat Science Team (LST) was held July 26-28, 2016, at South Dakota State University (SDSU) in Brookings, SD. LST co-chair Tom Loveland [USGS’s Earth Resources Observation and Science Center (EROS)] and Kevin Kephart [SDSU] welcomed more than 80 participants to the three-day meeting. That attendance at such meetings continues to increase—likely due to the development of new data products and sensor systems—further highlights the growing interest in the Landsat program. The main objectives of this meeting were to provide a status update on Landsat 7 and 8, review team member research activities, and to begin identifying priorities for future Landsat missions.

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

    International Nuclear Information System (INIS)

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

    2003-10-01

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

  17. Final IAEA research coordination meeting on plasma-interaction induced erosion of fusion reactor materials. October 9-11, 1995, Vienna, Austria. Summary report

    International Nuclear Information System (INIS)

    Langley, R.A.

    1995-12-01

    The proceedings and results of the Final IAEA Research Coordination Meeting on ''Plasma-interaction Induced Erosion of Fusion Reactor Materials'' held on October 9, 10 and 11, 1995 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of presentations made by the meeting participants, the results of a data survey and needs assessment for the erosion of plasma facing components and in-vessel materials, and recommendations regarding future work. (author). Refs, figs, tabs

  18. Study group meeting on steam generators for LMFBR's. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-07-01

    The Meeting organised by IAEA international working group on fast reactors which considered that the subject of sodium heated steam generators was a topic which needed study by the experts of several disciplines. For example: people who design such steam generators, specialists in the field of sodium water reactions, experts in material and water chemistry and members of the utilities who would be the customers for such units. Besides the exchange of large amount of information, it was considered that further special studies were necessary for the following subjects: materials; maintenance and repair; operating procedures and control of steam generators. A separate study of sodium-water reactions was recommended considering the safety aspects related to large water leakage and economic advantage of possible detection and protection against small water leaks.

  19. Study group meeting on steam generators for LMFBR's. Summary report

    International Nuclear Information System (INIS)

    1975-07-01

    The Meeting organised by IAEA international working group on fast reactors which considered that the subject of sodium heated steam generators was a topic which needed study by the experts of several disciplines. For example: people who design such steam generators, specialists in the field of sodium water reactions, experts in material and water chemistry and members of the utilities who would be the customers for such units. Besides the exchange of large amount of information, it was considered that further special studies were necessary for the following subjects: materials; maintenance and repair; operating procedures and control of steam generators. A separate study of sodium-water reactions was recommended considering the safety aspects related to large water leakage and economic advantage of possible detection and protection against small water leaks

  20. Meeting Report: 2013 PDA Virus & TSE Safety Forum.

    Science.gov (United States)

    Willkommen, Hannelore; Blümel, Johannes; Brorson, Kurt; Chen, Dayue; Chen, Qi; Gröner, Albrecht; Hubbard, Brian R; Kreil, Thomas R; Ruffing, Michel; Ruiz, Sol; Scott, Dorothy; Silvester, Glenda

    2014-01-01

    The report provides a summary of the presentations and discussions at the Virus & TSE Safety Forum 2013 organized by the Parenteral Drug Association (PDA) and held in Berlin, Germany, from June 4 to 6, 2013. The conference was accompanied by a workshop, "Virus Spike Preparations and Virus Removal by Filtration: New Trends and Developments". The presentations and the discussion at the workshop are summarized in a separate report that will be published in this issue of the journal as well. As with previous conferences of this series, the PDA Virus & TSE Safety Forum 2013 provided again an excellent opportunity to exchange information and opinions between the industry, research organizations, and regulatory bodies. Updates on regulatory considerations related to virus and transmissible spongiform encephalopathy (TSE) safety of biopharmaceuticals were provided by agencies of the European Union (EU), the United States (US), and Singapore. The epidemiology and detection methods of new emerging pathogens like hepatitis E virus and parvovirus (PARV 4) were exemplified, and the risk of contamination of animal-derived raw materials like trypsin was considered in particular. The benefit of using new sequence-based virus detection methods was discussed. Events of bioreactor contaminations in the past drew the attention to root cause investigations and preventive actions, which were illustrated by several examples. Virus clearance data of specific unit operations were provided; the discussion focused on the mechanism of virus clearance and on the strategic concept of viral clearance integration. As in previous years, the virus safety section was followed by a TSE section that covered recent scientific findings that may influence the risk assessment of blood and cell substrates. These included the realization that interspecies transmission of TSE by blood components in sheep is greater than predicted by assays in transgenic mice. Also, the pathogenesis and possibility of

  1. Summary Report of 1st Research Coordination Meeting on Development of Reference Database for Beta-delayed Neutron Emission

    International Nuclear Information System (INIS)

    Dillmann, Iris; Dimitriou, Paraskevi; Singh, Balraj

    2014-03-01

    A summary is given of the 1st Research Coordination Meeting of the new IAEA Coordinated Research Project (CRP) on Development of a Reference Database for Beta-delayed neutron emission data. Participants presented their work, reviewed the current status of the field with regards to individual precursors and aggregate data, and discussed the scope of the work to be undertaken. A list of priorities and task assignments was produced. (author)

  2. 75 FR 36427 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-06-25

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug Administration, HHS. ACTION: Notice. This notice...

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

    International Nuclear Information System (INIS)

    1993-01-01

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

  4. 76 FR 59142 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the...., [[Page 59143

  5. 2. IAEA research co-ordination meeting on 'Atomic and molecular data for fusion plasma diagnostics'. 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 2nd Research Co-ordination Meeting (RCM) of the Co-ordinated Research Project (CRP) on 'Atomic and Molecular Data for Fusion Plasma Diagnostics' held on 16-18 June 2003 at IAEA Headquarters, Vienna. During the course of the meeting the progress achieved to data was thoroughly reviewed. It was noted that during the course of the research several new areas of data needs were revealed. During detailed discussions proposals from all participants on ongoing data needs indicated that a one year extension of the CRP would be extremely valuable with an additional RCM to be held in 2004. A specific proposal for such an extension was formulated along with the summary of the results achieved to date. (author)

  6. Remedial action programs annual meeting: Meeting notes

    International Nuclear Information System (INIS)

    1987-01-01

    The US Department of Energy Grand Junction Projects Office was pleased to host the 1987 Remedial Action programs Annual Meeting and herein presents notes from that meeting as prepared (on relatively short notice) by participants. These notes are a summary of the information derived from the workshops, case studies, and ad hoc committee reports rather than formal proceedings. The order of the materials in this report follows the actual sequence of presentations during the annual meeting

  7. 76 FR 13643 - FDA Food Safety Modernization Act: Title III-A New Paradigm for Importers; Public Meeting

    Science.gov (United States)

    2011-03-14

    ... Act: Title III--A New Paradigm for Importers; Public Meeting AGENCY: Food and Drug Administration, HHS... announcing a public meeting entitled ``FDA Food Safety Modernization Act: Title III--A New Paradigm for... provided. Request special accommodations due By March 22, 2011.... Patricia M. Kuntze, 301- to disability...

  8. Survey Summary

    Data.gov (United States)

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

  9. Inventory of Federal energy-related environment and safety research for FY 1979. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1980-12-01

    The FY 1979 Federal Inventory contains information on 3506 federally funded energy-related environmental and safety research projects. The Inventory is published in two volumes: Volume I, an executive summary and overview of the data and Volume II, project listings, summaries, and indexes. Research and development (R and D) categories were reorganized into three main areas; environmental and safety control technology, technology impacts overview and assessments, and biological and environmental R and D and assessments. Federal offices submitting project data were: Council on Environmental Quality; Department of Agriculture; Department of Commerce; Department of Defense; Department of Energy; Department of Health, Education, and Welfare; Department of Housing and Urban Development; Department of the Interior; Department of Transportation; Environmental Protection Agency; National Aeronautics and Space Administration; Nuclear Regulatory Commission; National Science Foundation; Office of Technology Assessment; and Tennessee Valley Authority. The inventory also breaks out research sponsored by various federal agencies and the amount of funding provided by each in various research categories. The format and index system allows efficient access to information compiled. Users are able to identify projects by log agency, performing organization, principal investigator and subject

  10. Summary Report of Consultants' Meeting on Accuracy of Experimental and Theoretical Nuclear Cross-Section Data for Ion Beam Analysis and Benchmarking

    International Nuclear Information System (INIS)

    Abriola, Daniel; Dimitriou, Paraskevi; Gurbich, Alexander F.

    2013-11-01

    A summary is given of a Consultants' Meeting assembled to assess the accuracy of experimental and theoretical nuclear cross-section data for Ion Beam Analysis and the role of benchmarking experiments. The participants discussed the different approaches to assigning uncertainties to evaluated data, and presented results of benchmark experiments performed in their laboratories. They concluded that priority should be given to the validation of cross- section data by benchmark experiments, and recommended that an experts meeting be held to prepare the guidelines, methodology and work program of a future coordinated project on benchmarking.

  11. 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)

  12. Summary of the Accelerator Meeting

    International Nuclear Information System (INIS)

    Lia Merminga

    2006-01-01

    The summary of the paper is: (1) A compelling scientific case is developing for a high luminosity, polarized electron-ion collider, to address fundamental questions in hadron Physics. (2) Much progress over the past years: Design concepts are maturing through innovation and design optimization. (3) Electron cooling is prerequisite for all EIC design scenarios. A rigorous electron cooling R and D program established at BNL. (4) Important to continue collaboration and cross-fertilization of ideas among different design options. (5) Thank you to all the speakers for outstanding and thought-provoking presentations

  13. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection; 3. Congreso Regional sobre Seguridad Radiologica y Nuclear, Congreso Regional IRPA y 3. Congreso Peruano de Proteccion Radiologica. Libro de Resumenes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting.

  14. 75 FR 52303 - Notice of Meeting; Siskiyou Resource Advisory Committee Meeting at New Location

    Science.gov (United States)

    2010-08-25

    ... DEPARTMENT OF AGRICULTURE Forest Service Notice of Meeting; Siskiyou Resource Advisory Committee Meeting at New Location SUMMARY: The Siskiyou County Resource Advisory Committee (RAC) will hold its last two meetings in 2010 at a new location. DATES: The meetings will be held on September 20 and October...

  15. CSNI specialist meeting on simulators and plant analyzers

    International Nuclear Information System (INIS)

    Miettinen, J.; Holmstroem, H.

    1994-01-01

    The Specialist Meeting on Simulators and Plant Analyzers, held in June 9-12, 1992, in Lappeenranta, Finland, was sponsored by the Committee on the Safety on Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organized in collaboration with the Technical Research Centre of Finland (VTT) and the Lappeenranta Technical University of Technology (LTKK). All the presented papers were invited and devided into four sessions. In the first session the objectives, requirements and consepts of simulators were discussed against present standards and guidelines. The second session focused on the capabilities of current analytical models. The third session focused on the experiences gained so far from the applications. The final fourth session concentrated on simulators, which are currently under development, and future plans with regard to both development and utilization. At the end of the meeting topics of the meeting were discussed at the panel discussion. Summaries of the sessions and shortened version of the panel discussion are included into the proceeding. (orig.)

  16. 77 FR 55837 - Board Meeting

    Science.gov (United States)

    2012-09-11

    ... FARM CREDIT SYSTEM INSURANCE CORPORATION Board Meeting AGENCY: Farm Credit System Insurance Corporation. ACTION: Regular meeting. SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). Date and Time: The meeting of the Board will be held...

  17. 40 CFR 35.532 - Requirements summary.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Requirements summary. 35.532 Section 35.532 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE....532 Requirements summary. (a) Applicants and recipients of Performance Partnership Grants must meet...

  18. 40 CFR 35.132 - Requirements summary.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Requirements summary. 35.132 Section 35.132 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Requirements summary. Applicants and recipients of Performance Partnership Grants must meet: (a) The...

  19. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    International Nuclear Information System (INIS)

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980

  20. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.

  1. 75 FR 76006 - Regular Meeting

    Science.gov (United States)

    2010-12-07

    ... FARM CREDIT SYSTEM INSURANCE CORPORATION Regular Meeting AGENCY: Farm Credit System Insurance Corporation Board. ACTION: Regular meeting. SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). Date and Time: The meeting of the Board will be held...

  2. 77 FR 2541 - Board Meeting

    Science.gov (United States)

    2012-01-18

    ... FARM CREDIT SYSTEM INSURANCE CORPORATION Board Meeting AGENCY: Farm Credit System Insurance Corporation Board; Regular Meeting. SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). DATE AND TIME: The meeting of the Board will be held at the...

  3. 76 FR 3629 - Regular Meeting

    Science.gov (United States)

    2011-01-20

    ... Meeting SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). Date and Time: The meeting of the Board will be held at the offices of the Farm... meeting of the Board will be open to the [[Page 3630

  4. Model summary report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Vahlund, Fredrik

    2006-10-15

    This document is the model summary report for the safety assessment SR-Can. In the report, the quality assurance measures conducted for the assessment codes are presented together with the chosen methodology. In the safety assessment SR-Can, a number of different computer codes are used. In order to better understand how these codes are related Assessment Model Flowcharts, AMFs, have been produced within the project. From these, it is possible to identify the different modelling tasks and consequently also the different computer codes used. A large number of different computer codes are used in the assessment of which some are commercial while others are developed especially for the current assessment project. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined: It must be demonstrated that the code is suitable for its purpose; It must be demonstrated that the code has been properly used; and, It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. Although the requirements are identical for all codes, the measures used to show that the requirements are fulfilled will be different for different codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented and it is shown how the requirements are met.

  5. Model summary report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Vahlund, Fredrik

    2006-10-01

    This document is the model summary report for the safety assessment SR-Can. In the report, the quality assurance measures conducted for the assessment codes are presented together with the chosen methodology. In the safety assessment SR-Can, a number of different computer codes are used. In order to better understand how these codes are related Assessment Model Flowcharts, AMFs, have been produced within the project. From these, it is possible to identify the different modelling tasks and consequently also the different computer codes used. A large number of different computer codes are used in the assessment of which some are commercial while others are developed especially for the current assessment project. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined: It must be demonstrated that the code is suitable for its purpose; It must be demonstrated that the code has been properly used; and, It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. Although the requirements are identical for all codes, the measures used to show that the requirements are fulfilled will be different for different codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented and it is shown how the requirements are met

  6. Meeting of senior officials on managing nuclear knowledge. Summary meeting report

    International Nuclear Information System (INIS)

    2002-01-01

    In response to the recommendations of several Agency advisory committees, e.g. INSAG, SAGNE 2002, SAGNA, SAGTAC, to address issues related to nuclear knowledge management, the IAEA convened a meeting on Managing Nuclear Knowledge with senior representatives from Member States. The purpose of the meeting was to sharpen awareness and understanding of the emerging concerns about the maintenance and preservation of knowledge and expertise in nuclear science, technology and applications and to better comprehend the role of the Agency in this process. The meeting was attended by more than 70 participants from 35 Member States and 4 international organizations, representing academic leaders, senior level executives, managers and governmental officials. This report includes statements and recommendation on possible activities to be undertaken by the IAEA

  7. IAEA advisory group meeting on nuclear data for radiation damage assessment and related safety aspects, Vienna, 12-16 October 1981

    International Nuclear Information System (INIS)

    Kocherov, N.

    1982-01-01

    This Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was convened by the IAEA Nuclear Data Section, at IAEA Headquarters in Vienna, Austria, from 12-16 October 1981. The meeting was attended by 34 participants from 15 countries and 2 international organizations. The main objective of the meeting was to review the requirements for and the status of nuclear data needed for radiation damage estimates in reactor structural materials and related reactor safety aspects, and to develop recommendations to the Nuclear Data Section of the IAEA for its future activities in this field. (author)

  8. Safety Assessment for Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

  9. Development of IAEA description of passive safety and subsequent thoughts

    Energy Technology Data Exchange (ETDEWEB)

    Lang, P M [USDOE, Washington, DC (United States)

    1996-12-01

    The description of passive components and systems published by the IAEA in its TECDOC-626 was developed in the course of a Technical Committee Meeting held in Sweden and two subsequent Consultants Meetings held in Vienna. This description is reviewed and discussed in terms of the philosophies behind it, alternatives considered, problems encountered, and conclusions drawn. Also discussed is an Appendix to the TECDOC, which illustrates the spectrum of possibilities from passive to active by describing four typical categories of passivity. Subsequent thoughts on passive safety include a discussion of its advantages and disadvantages, concluding with a summary of current views and problems with it. (author). 8 refs.

  10. The Nordic programme for nuclear safety 1990-1993. Report for 1992

    International Nuclear Information System (INIS)

    1993-04-01

    The annual report contains the coordinators' summary of the results so far achieved by the in all 18 current projects in which 200 persons are taking part. In some cases the project leader's account is included. An overview is given of the programme's costs and orders during 1992 in relation to the subsidies given to the individual projects. The fields covered by these projects are emergency readiness in radiation situations which are not normal, nuclear wastes and their disposal, radioecology, reactor safety - knowledge readiness, and coordination efforts. An economical overview is given and English summaries of the projects presented at the summer meeting in 1992 are presented. A list of the names of the members of the Nordic Nuclear Safety Research members in the syndicate and reference groups is included in the publication, and a brief description is to be found of the institution's activities. (AB) (78 refs.)

  11. 'AER Working Group D On WWER Safety Analysis' Report Of The Meeting In Pisa, Italy, 26-27 April 2006

    International Nuclear Information System (INIS)

    Siltanen, P.

    2006-01-01

    AER Working Group D on WWER reactor safety analysis held its 15 t h meeting in Grand Hotel Duomo in Pisa, Italy during the period 26-27 April 2006. The meeting was hosted by the University of Pisa following the fourth workshop on the OECD/DOE/CEA WWER-1000 Coolant Transient Benchmark (W1000-CT) held at the same location on 24-25 April. Altogether 15 participants attended the Working Group D meeting, 11 from AER member organizations and 4 guests from non-member organizations. The coordinator for the working group, Mr. P. Siltanen (FNS) served as chairman. In addition to general information exchange on recent activities in the participating organizations, the topics of the meeting included: 1) Code development and benchmarking for reactor dynamics applications. 2) Safety analysis methodology and results. 3) Future activities. A list of participants and a list of handouts distributed at the meeting are attached to the report (Author)

  12. Summary report on the use of plant safety performance indicators

    International Nuclear Information System (INIS)

    2001-09-01

    In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. In parallel, a joint CNRA/CSNI group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's) and these are the ones that this report deals with. This report presents the work performed by the joint CNRA/CSNI task group mentioned above. It provides a summary of the sets of PI's being used by different regulatory bodies and WANO, it describes the national practices on the use of PI's and proposes a set of PI's that could be used nationally describing regulatory effectiveness and also as a basis for an international system. The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001. Each participant provided a brief description of the PI System at his organisation and its usage. The group identified a list of PI's that are recommended to be used nationally by regulators. This paper has been elaborated based on the information exchanged and discussions held in the February meeting. The participating countries (Spain, Finland, US, Sweden) and WANO were asked to provide an overview of systems in use. The presently used Performance Indicators were reviewed in a three steps process. 1. First indicators used in at least two agencies were identified. 2. The second step was to identify the most used indicators. 3. The third step was to

  13. Summary report of the IAEA advisory group meeting on nuclear data for neutron multiplication in fusion-reactor first-wall and blanket materials

    International Nuclear Information System (INIS)

    Muir, D.W.; Pashchenko, A.B.

    1992-09-01

    The present Report contains the Summary of the IAEA Advisory Group Meeting on Nuclear Data for Neutron Multiplication in Fusion-Reactor First-Wall and Blanket Materials, which was hosted by the Southwest Institute of Nuclear physics and Chemistry (SWINPC) at Chengdu, China and held from 19-21 November 1990. This AGM was organized by the IAEA Nuclear Data Section (NDS), with the cooperation and assistance of local organizers at the SWINPC. The papers which the participants prepared for and presented at the meeting will be published as an INDC report. (author)

  14. Summary Record of the Fifth Meeting of Records, Knowledge and Memory (RK and M) Across Generations

    International Nuclear Information System (INIS)

    2013-01-01

    Preservation of Records, Knowledge and Memory (RK and M) across Generations is an initiative under the RWMC in the area of knowledge consolidation and transfer. Disposal in engineered facilities built in stable, deep geological formations is the reference means for permanently isolating long-lived radioactive waste from the biosphere. However, there is no intention to forgo, at any time, knowledge and awareness either of the repository or of the waste that it contains. The cultural dimension of preserving RK and M is an important subject. Overall, long-term preservation of RK and M is a multidisciplinary work area in which much learning is expected over the coming years. This is the task of the RWMC's RK and M initiative. A major outcome will be a menu-driven document that - the RK and M Wiki - that will allow people to identify the elements of a strategic action plan for RK and M preservation. This document is a summary record of the 5. Meeting of the RK and M initiative. The summary is made of 8 items: 1 - Introduction (Claudio Pescatore); 2 - Updates: Wiki Status and Plans (Philippe Maupai, Claudio Pescatore), Glossary (Stephan Hotzel, Claudio Pescatore, Anne Claudel), Bibliography (Anne Claudel, Richard Ferch), Set of Essential Records- SER (Claire Mays); 3 - Documenting Phase I: Master-plan for finalising Phase I (Claudio Pescatore); 4 - Discussion of articles by project participants: The Bibliography and its Analysis (Richard Ferch, Abe Van Luik), Guiding principles (Erik Setzman, Jean-Noel Dumont), Decisions and actions, The connection to safety (Claudio Pescatore, Mareike Rueffer), Archives (Anne Claudel, Sofie Tunbrant), Cultural heritage (Jantine Schroeder, Thomas Kaiserfeld), Causes of loss of Records, Knowledge and Memory (Simon Wisbey, Arne Berckmans); 5 - Regulatory aspects (Richard Ferch, Peter Ormai), Supranational Mechanisms (Jean-Noel Dumont, Anne Claudel), Markers (Jantine Schroeder, Jozsef Fekete), General comments on Strategic Articles

  15. Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

    International Nuclear Information System (INIS)

    2010-02-01

    In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

  16. Improvement of measurements, theoretical computations and evaluations of neutron induced helium production cross sections. Summary report on the third and final research co-ordination meeting

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1996-09-01

    The present report contains the Summary of the Third and Final IAEA Research Co-ordination Meeting (RCM) on ''Improvement of Measurements, Theoretical Computations and Evaluations of Neutron Induced Helium Production Cross Sections'' which was hosted by the Tohoku University and held in Sendai, Japan, from 25 to 29 September 1995. This RCM was organized by the IAEA Nuclear Data Section (NDS), with the co-operation and assistance of local organizers from Tohoku University. Summarized are the proceedings and results of the meeting. The List of Participants and meeting Agenda are included. (author)

  17. Summary Report of the 1. Research Coordination Meeting on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF)

    International Nuclear Information System (INIS)

    Trkov, A.; Greenwood, L.R.; Simakov, S.P.

    2013-09-01

    In accordance with the recommendations of the International Nuclear Data Committee in May 2012, the Nuclear Data Section of IAEA has initiated a new Coordinated Research Project (CRP number F41031) with the main goal to test, validate and improve the international dosimetry library for fission and fusion (IRDFF). The output of this CRP will be a reference dosimetry database of cross sections and decay data with corresponding documentation. It will serve to the needs of fission, fusion and accelerator applications. The first Research Coordination Meeting (RCM) was held 1 to 5 July 2013 in IAEA. At this meeting, the attendees discussed the objectives of the whole CRP, presented their contributions and elaborated on consolidated recommendations and actions for implementation over the next 1.5 year period. This Summary Report documents the individual contributions and joint decisions made during this meeting. (author)

  18. 78 FR 32295 - Commission Meeting

    Science.gov (United States)

    2013-05-29

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... business meeting are contained in the Supplementary Information section of this notice. DATES: June 20...

  19. 77 FR 10599 - Commission Meeting

    Science.gov (United States)

    2012-02-22

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... business meeting are contained in the Supplementary Information section of this notice. DATES: March 15...

  20. 78 FR 12412 - Commission Meeting

    Science.gov (United States)

    2013-02-22

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... business meeting are contained in the Supplementary Information section of this notice. DATES: March 21...

  1. 78 FR 52601 - Commission Meeting

    Science.gov (United States)

    2013-08-23

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... meeting are contained in the Supplementary Information section of this notice. DATES: September 19, 2013...

  2. 77 FR 70204 - Commission Meeting

    Science.gov (United States)

    2012-11-23

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... meeting are contained in the SUPPLEMENTARY INFORMATION section of this notice. DATES: December 14, 2012...

  3. 78 FR 69517 - Commission Meeting

    Science.gov (United States)

    2013-11-19

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... meeting are contained in the Supplementary Information section of this notice. DATES: December 12, 2013...

  4. 77 FR 52106 - Commission Meeting

    Science.gov (United States)

    2012-08-28

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... business meeting are contained in the Supplementary Information section of this notice. DATES: September 20...

  5. Statement to Second Extraordinary Meeting of Contracting Parties to Convention on Nuclear Safety, 27 August 2012, Vienna, Austria

    International Nuclear Information System (INIS)

    Amano, Y.

    2012-01-01

    Full Text: I am pleased to address this Second Extraordinary Meeting of the Contracting Parties to the Convention on Nuclear Safety. This important meeting will be closely watched by the global nuclear community. I know you will make good use of this opportunity to consider further measures to strengthen nuclear safety throughout the world in the light of the lessons which we are still learning from the Fukushima Daiichi accident. One year after the adoption of the IAEA Action Plan on Nuclear Safety, significant progress has been made in several key areas. These include the assessment of safety vulnerabilities of nuclear power plants, strengthening IAEA peer review services, improving emergency preparedness and response capabilities and reviewing IAEA safety standards. Your work this week will address the request to Contracting Parties, expressed in the Action Plan, to explore mechanisms to enhance the effective implementation of Safety Conventions and to consider proposals to amend the Convention on Nuclear Safety. You will recall that last year's Ministerial Declaration stressed 'the importance of universal adherence to, and the effective implementation and continuous review of, the relevant international instruments on nuclear safety'. The Action Plan encouraged Member States to work cooperatively to maximize the lessons learned from the Fukushima Daiichi accident and to produce concrete results as soon as possible. The IAEA has reported periodically to Member States about its work to implement the Action Plan. We have also organised a number of international expert meetings to analyse technical aspects of the accident and ensure that the right lessons are learned. The results of this Extraordinary Meeting will provide an important input to future considerations of implementation of the Action Plan. Our Member States will review implementation at the Agency's 56th General Conference next month, while the Fukushima Ministerial Conference on Nuclear Safety in

  6. Conference summaries

    International Nuclear Information System (INIS)

    1991-01-01

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

  7. Proceedings of the international symposium on safety related measurements in PWRs: Topic of the first meeting: 'Temperature and level measurements'

    International Nuclear Information System (INIS)

    2001-09-01

    Numerous teams of experts from several countries deal with theme of measurement important for safety operation of WWER reactors. These special teams have a need to meet at various opportunities to change their experience. As an example I can mention meeting of experts from Russia , Germany, France and Slovakia at completion and reconstruction of Slovak NPP, at modernisation of Russian and Bulgarian NPP. Mentioned meetings have invoked an idea of participants to organise a common action aimed at measurement important for safety operation of WWER, that participants can change their experience from mentioned area at welcome environment of symposium. Therefore, at meeting of experts from Siemens, INCOR and VUJE at the end of the year 2000 participants agreed on realisation of such common action. Participants have taken orientation at all safety measurements for very deep topic. Therefore, they have decided in respect of this first meeting of symposium to give consideration to only some special measurements in particular to temperature and surface. In case of interest there is possible to take focus at other type of measurements. Slovakia has been chosen for the first meeting place on basis of economic reasons and also because a number of improvements of standard reactor temperature measuring procedures have been implemented here that over passed its frontiers. In addition the first fail-safe level measuring in reactor pressure vessel has been effectuated in Slovakia

  8. 77 FR 28420 - Commission Meeting

    Science.gov (United States)

    2012-05-14

    ... SUSQUEHANNA RIVER BASIN COMMISSION Commission Meeting AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: The Susquehanna River Basin Commission will hold its regular business meeting on... meeting are contained in the Supplementary Information section of this notice. DATES: June 7, 2012, at 9...

  9. First research co-ordination meeting on development of reference charged particle cross section data base for medical radioisotope production. Summary report

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1996-03-01

    The present report contains the summary of the First Research Co-ordination Meeting on ''Development of Reference Charged Particle Cross Section Data Base for Medical Radioisotope Production'', held at the IAEA Headquarters, Vienna, from 15 to 17 November 1995. The project focuses on monitor reactions and production reactions for gamma emitters and positron emitters induced with light charged particles of incident energies up to about 100 MeV. Summarized are technical discussions and the resulting work plan of the Coordinated Research Programme, including actions and deadlines. Attached are an information sheet on the project, the agenda and a list of participants of the meeting. Also attached is brief information on the adjacent Consultant's Meeting on ''Automated Synthesis Systems for the Cyclotron Production of 18 F and 123 I and their Labeled Radiopharmaceuticals''. (author)

  10. 76 FR 40735 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-07-11

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... East, Adelphi, MD. The conference center telephone number is: 301 985-7300. Contact Person: Kalyani...

  11. 75 FR 10490 - Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management...

    Science.gov (United States)

    2010-03-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management Advisory... Drug Safety and Risk Management Advisory Committee. General Function of the Committees: To provide...

  12. High committee for nuclear safety transparency and information. October 8, 2009 meeting

    International Nuclear Information System (INIS)

    2009-10-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main points: 1 - the progress of the different working groups work: elaboration of a communication scale, comparable to the INES scale, for the evaluation of environmental radioactivity, the realisation of a web site for the HCTISN, the question of transparency and secrecy around the maritime transportation of radioactive materials after the visit by the High Committee of two ships from the British INS company; 2 - the management of radioactive wastes with the concept of storage reversibility: political, technical and decisional aspects, position of the National Evaluation Committee for the researches and studies relative to radioactive materials and wastes management (CNE), position of the ANCLI (French national association of local information commissions), debate; 3 - the shortage of radio-physicists in France and the information of populations and patients (declaration of incidents). Some miscellaneous points are reported as well: the first draft of the first annual report of the HCTISN, development of a societal approach for the research programs of the French institute of radiation protection and nuclear safety (IRSN), validation of a collaboration proposal with the ANCLI. (J.S.)

  13. Conference summaries

    International Nuclear Information System (INIS)

    1988-01-01

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

  14. Meeting summary housing and registration information

    Science.gov (United States)

    The 1986 Ocean Sciences Meeting of the American Geophysical Union and the American Society of Limnology and Oceanography (ASLO) will be held January 13-17, 1986, in New Orleans, La., at the Fairmont Hotel. Co-sponsoring societies are the Acoustical Society of America (ASA), the American Meteorological Society (AMS), the Marine Technology Society (MTS), and the Institute of Electrical and Electronics Engineers, Oceanic Engineering Society (OES).Some of the most compelling problems in science and technology span two or more disciplines, and this is especially true of oceanography, which is an amalgamation of several sciences with technology. This meeting will cover topics that include physical and biological oceanography, atmospheric sciences, chemical and geological oceanography, underwater acoustics, and ocean technology.

  15. 76 FR 37375 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2011-06-27

    ... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions... who wish to participate must register at least seven (7) days in advance of the meeting/conference... registration. Anyone requiring special accommodations should contact Mr. Joy at least seven (7) days in advance...

  16. Safety assessment of proposed modifications of Ignalina nuclear power plant. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1995-09-01

    The objective of the meeting was to further discuss previous findings and recommendations and their application to the particular situation of the Ignalina NPP. Since design information and a series of proposed modifications for INPP had been prepared by the main RBMK designer, Research and Development Institute for Power Engineering (RDIPE), it was considered appropriate to conduct the meeting in two parts, the first from 17 to 22 October 1994, at RDIPE headquarters in Moscow and the second from 24 to 28 October 1994, at the plant site in Lithuania. Twelve international experts and IAEA staff participated in the meetings, together with a large group of RDIPE specialists and plant staff. The review covered five topical areas: core monitoring and control; pressure boundary integrity; accident migration; safety and support systems and instrumentation and control. A summary of the reviews in each technical areas is given in this report. Appendices 1 and 5 present the records of the reviews and detailed findings and recommendations in each topical area. The experts strongly supported the effort to develop a new extended safety analysis report. They also stressed the need for close monitoring of the fuel channel conditions and the need for an integrated approach for the upgrading of the control and safety systems. Refs, figs, tabs

  17. 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

  18. Thirteenth meeting of representatives of RCA Member States

    International Nuclear Information System (INIS)

    1986-07-01

    The 13th Meeting of Member States of RCA (Regional Co-operative Agreement for Research, Development and Training Related to Nuclear Science and Technology) was held on 26 September 1984 in Vienna. This document constitutes the report of that meeting. It includes the list of participants, agenda, summary of discussions, and 1984 costing table. The Report of Recommendations for the meeting consisted of the Summary Report of the Sixth RCA Working Group Meeting held in Kalpakkam, India, 20-23 March 1984. This Summary Report dealt with such topics as RCA research projects (including nuclear techniques to improve legume and buffalo production, radiosterilization of medical supplies, maintenance of nuclear instruments, isotope applications in hydrology and sedimentology), progress of the RCA/UNDP Industrial Project, and future programmes and budget

  19. 78 FR 2677 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-01-14

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... before February 7, 2013. Time allotted for each presentation may be limited. If the number of registrants...

  20. 76 FR 59143 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2011-09-23

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the..., Adelphi, MD. The conference center telephone number is 301-985-7300. Contact Person: Kalyani Bhatt, Center...

  1. On application of CFD codes to problems of nuclear reactor safety

    International Nuclear Information System (INIS)

    Muehlbauer, Petr

    2005-01-01

    The 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' held in May 2002 at Aix-en-Province, France, recommended formation of writing groups to report the need of guidelines for use and assessment of CFD in single-phase nuclear reactor safety problems, and on recommended extensions to CFD codes to meet the needs of two-phase problems in nuclear reactor safety. This recommendations was supported also by Working Group on the Analysis and Management of Accidents and led to formation oaf three Writing Groups. The first writing Group prepared a summary of existing best practice guidelines for single phase CFD analysis and made a recommendation on the need for nuclear reactor safety specific guidelines. The second Writing Group selected those nuclear reactor safety applications for which understanding requires or is significantly enhanced by single-phase CFD analysis, and proposed a methodology for establishing assesment matrices relevant to nuclear reactor safety applications. The third writing group performed a classification of nuclear reactor safety problems where extension of CFD to two-phase flow may bring real benefit, a classification of different modeling approaches, and specification and analysis of needs in terms of physical and numerical assessments. This presentation provides a review of these activities with the most important conclusions and recommendations (Authors)

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

    Energy Technology Data Exchange (ETDEWEB)

    Abriola, D.; Tuli, J.

    2009-03-23

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

  3. Summary Record of the Twenty-Sixth Meeting of the Working Party on International Nuclear Data Evaluation Co-operation

    International Nuclear Information System (INIS)

    Dupont, Emmeric

    2014-01-01

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countries) and CENDL (China) in close co-operation with the Nuclear Data Section of the International Atomic Energy Agency (IAEA). The working party was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation, and related topics, and to provide a framework for co-operative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint evaluation and/or measurement efforts. This document is the executive summary of WPEC's 26. meeting held in 2014. It presents a brief review of the 2 days meeting in particular the Reports on experimental activities in Europe, Japan, USA and China, the Brief progress reports from the evaluation projects (ENDF, JEFF, JENDL, ROSFOND, CENDL, IAEA, TENDL) with the discussion of future plans, the Review of final or near-final subgroup reports, the Status of ongoing subgroups, the Proposals for new subgroups and some information about Conferences and meetings of interest to the nuclear data community. A list of participants and a list of reports presented at this meeting are attached in appendix

  4. Statistical summary 1990-91

    International Nuclear Information System (INIS)

    1991-01-01

    The information contained in this statistical summary leaflet summarizes in bar charts or pie charts Nuclear Electric's performance in 1990-91 in the areas of finance, plant and plant operations, safety, commercial operations and manpower. It is intended that the information will provide a basis for comparison in future years. The leaflet also includes a summary of Nuclear Electric's environmental policy statement. (UK)

  5. Final summary report of the Nordic Nuclear Safety Research Program 1998-2001; Sammanfattning av det nordiska forsknings-programmet for karnsakerhet

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T. (ed.)

    2002-11-01

    The results of the 1998 - 2001 NKS program are presented in the form of executive summaries, highlighting the conclusions, recommendations and other findings and results of the six projects carried out during that period. The titles of the six projects are: Risk assessment and strategies for safety (NKS/SOS-1); Reactor safety (NKS/SOS-2); Radioactive waste (NKS/SOS-3); Nuclear Emergency preparedness (NKS/BOK-1); Radiological and environmental consequences (NKS/BOK-2); Nuclear threats from Nordic surroundings (NKS/SBA-1) (ln)

  6. A cost summary applicable to seismic construction and maintenance of nuclear safety related piping

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1995-01-01

    This paper presents a summary of costs applicable to nuclear power plant piping for an earthquake defined as 0.2 SSE-PGA as a function of three eras of initial construction: 1967--1974, 1974--1981 and 1981--1990. Costs have been presented for both new construction and maintenance in operating plants using both the original PSAR-FSAR design criteria and current SRP requirements. It is recommended that the cost information contained in this report be considered in evaluating the cost benefit relationships associated with current and proposed future changes in seismic design procedures applicable to safety-related piping systems

  7. AER working group D on WWER safety analysis - report of the 2007 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2007-01-01

    The AER working group D on WWER reactor safety analysis held its sixteenth meeting in Paris, France during the period 08-09 May 2007. The meeting was hosted by the CEA France. It followed the final workshop on the OECD/DOE/CEA WWER-1000 Coolant Transient Benchmark held at 07 May. Altogether 11 participants attend the meeting of the working group D, 7 from AER member organizations and 4 guests from non-member organizations. The co-ordinator of the working group, Mr. S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics: -Code development and benchmarking for reactor dynamics applications; -Safety analysis methodology and results; -Future activities. New solutions for three different benchmarks were presented and discussed. These are the Second AER Dynamic Benchmark on control rod ejection at hot zero power (S. Kliem, FZD), the WWER-1000 Coolant Transient Benchmark (E. Syrjaelahti, VTT) and the stationary AER-FCM101 Benchmark considering a WWER-1000 reactor (C. Parisi, UniPisa). A. Kereszturi (AEKI) presented a statistical evaluation of the possibility to observe a fuel assembly mis loading event. The second presentation of E. Syrjaelahti was dedicated to the description how best-estimate coupled code calculations at VTT are supported by uncertainty and sensitivity analyses. K. Velkov (GRS) presented preliminary results of BIPR8KN/ATHLET calculations with a very detailed resolution of the calculation grid on the assessment of coolant mixing inside WWER-1000 assembly heads. Coolant mixing experiments at three different mixing test facilities, modeling different reactor types, were presented and compared by S. Kliem. A calculation study using the coupled code system KORSAR/GP on the consequences of the injection of a slug of un borated water into the reactor core was

  8. 75 FR 30859 - Meeting of the Public Safety Officer Medal of Valor Review Board

    Science.gov (United States)

    2010-06-02

    ... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions... participate must register at least seven (7) days in advance of the meeting/conference call by contacting Mr.... Anyone requiring special accommodations should contact Mr. Joy at least seven (7) days in advance of the...

  9. 78 FR 16271 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

    Science.gov (United States)

    2013-03-14

    ...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... presentation may be limited. If the number of registrants requesting to speak is greater than can be reasonably...

  10. 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

  11. Summary record of the topical session of 18. Meeting of the IGSC

    International Nuclear Information System (INIS)

    Hedin, A.; Leigh, C.

    2016-01-01

    The aim for the session was: To review and evaluate the current technologies of radioactive waste disposal in geological repositories. The technologies discussed could be technologies used to provide worker safety during the operational period of the repository as well as technologies that are included in the repository design to enhance the safety case. The topic is of interest especially regarding the aspects of it that apply to establishing the safety case. The Program Committee had offered the following guidance to the presenters: Briefly describe the design of your repository and EBS components; Explain testing activities and performance demonstration of the tested components (e.g. disposal containers, buffer / bentonite pellets, emplacement equipment, etc.); If possible please provide fabrication and testing details of physical prototypes, the ability to manufacture using proven processes and practices; Are there any plans for a demonstration/pilot phase? What are the objectives? Does the demonstration/pilot phase include an active or inactive operation or both? What will be demonstrated? Are there plans for a full-scale demonstration of the integrated disposal sequence (and back-filling) under realistic repository conditions, remote handling and radiation shielding equipment? How does a pilot phase support public dialogue? If applicable, please explain the objectives and rationale for performance confirmation. Given this guidance, 10 presentations from eight countries, Sweden, Finland, Canada, Germany, France, United States, Hungary and Japan, were submitted for the session. Perspectives from both the implementer and the regulator were offered for several countries. The questions throughout the day led to interesting discussions that were further developed in the plenary discussion at the end of the day. This document is a summary of the 10 presentations and of the key observations and conclusions from the discussions

  12. Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects

    International Nuclear Information System (INIS)

    1997-01-01

    Design and management of nuclear fuel has undergone a strong evolution process during past years. The increase of the operating cycle length and of the discharge burnup has led to the use of more advanced fuel designs, as well as to the adoption of fuel efficient operational strategies. The analysis of recent operational experience highlighted a number of issues related to nuclear fuel and control rod events raising concerns about the safety aspects of these new designs and operational strategies, which led to the organisation of this Specialists Meeting on fuel and control rod issues. The meeting was intended to provide a forum for the exchange of information on lessons learned and safety concern related to operating experience with fuel and control rods (degradation, reliability, experience with high burnup fuel, and others). After an opening session 6 papers), this meeting was subdivided into four sessions: Operating experience and safety concern (technical session I - 6 papers), Fuel performance and operational issues (technical session II - 7 papers), Control rod issues (technical session III - 9 papers), Improvement of fuel design (technical session IV.A - 4 papers), Improvement on fuel fabrication and core management (technical session IV.B - 6 papers)

  13. High Committee for transparency and information on nuclear safety: Annual activity report (January 2010 - December 2010)

    International Nuclear Information System (INIS)

    2010-01-01

    After a description of the operation of the French 'High Committee for transparency and information on nuclear safety' (HCTISN), of its missions, its organisation and its means, the progress report presents the High Committee activity for 2010 with summaries of its report on the transparency of nuclear material and waste management, its meetings, its work groups, its visits and participations to other events

  14. Rational quantitative safety goals: a summary

    International Nuclear Information System (INIS)

    Unwin, S.D.; Hayns, M.R.

    1984-08-01

    We introduce the notion of a Rational Quantitative Safety Goal. Such a goal reflects the imprecision and vagueness inherent in any reasonable notion of adequate safety and permits such vagueness to be incorporated into the formal regulatory decision-making process. A quantitative goal of the form, the parameter x, characterizing the safety level of the nuclear plant, shall not exceed the value x 0 , for example, is of a non-rational nature in that it invokes a strict binary logic in which the parameter space underlying x is cut sharply into two portions: that containing those values of x that comply with the goal and that containing those that do not. Here, we utilize an alternative form of logic which, in accordance with any intuitively reasonable notion of safety, permits a smooth transition of a safety determining parameter between the adequately safe and inadequately safe domains. Fuzzy set theory provides a suitable mathematical basis for the formulation of rational quantitative safety goals. The decision-making process proposed here is compatible with current risk assessment techniques and produces results in a transparent and useful format. Our methodology is illustrated with reference to the NUS Corporation risk assessment of the Limerick Generating Station

  15. 78 FR 4847 - Board Meeting

    Science.gov (United States)

    2013-01-23

    ... FARM CREDIT SYSTEM INSURANCE CORPORATION Board Meeting AGENCY: Farm Credit System Insurance Corporation. SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). DATE AND TIME: The meeting of the Board will be held at the offices of the Farm...

  16. 75 FR 53966 - Regular Meeting

    Science.gov (United States)

    2010-09-02

    ... FARM CREDIT SYSTEM INSURANCE CORPORATION Regular Meeting AGENCY: Farm Credit System Insurance Corporation Board. SUMMARY: Notice is hereby given of the regular meeting of the Farm Credit System Insurance Corporation Board (Board). DATE AND TIME: The meeting of the Board will be held at the offices of the Farm...

  17. 76 FR 9636 - Public Meeting

    Science.gov (United States)

    2011-02-18

    ... DEPARTMENT OF THE TREASURY United States Mint Public Meeting ACTION: Notification of Citizens Coinage Advisory Committee March 1, 2011, Public Meeting. SUMMARY: Pursuant to United States Code, Title... (CCAC) public meeting scheduled for March 1, 2011. Date: March 1, 2011. Time: 10 a.m. to 1 p.m. Location...

  18. International Experts’ Meeting on Reactor and Spent Fuel Safety in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant. Presentations

    International Nuclear Information System (INIS)

    2012-01-01

    The primary objectives of this International Experts’ Meeting (IEM) were: to analyse relevant technical aspects of reactor and spent nuclear fuel management safety and performance related to severe accidents; to review what is known to date about the accident at the Fukushima Daiichi nuclear power plant in order to understand more fully its root causes; and to share the lessons learned from the accident. The meeting identified the necessary priorities for further actions in these areas in different power reactor types, focusing in particular on boiling water reactors (BWRs) and pressurized water reactors (PWRs). The meeting provided a forum for discussions and exchange of information among technical experts from Member States on reactor and spent nuclear fuel safety and performance under severe conditions. The meeting was of particular interest to technical experts from utilities, research and design organizations, regulatory bodies, manufacturing and service companies and other stakeholders. In particular, the objectives of the meeting was to: • Identify and analyse reactor and spent nuclear fuel safety and performance issues; • Consider the design, engineering and analysis of current and new systems for accident prevention and mitigation; • Exchange information on national assessments of reactor and spent nuclear fuel safety and performance; and • Identify potential priority areas for research and development, technology development and management

  19. Safety related maintenance in the framework of the reliability centered maintenance concept

    International Nuclear Information System (INIS)

    1992-07-01

    Elevated safety requirements and ever increasing costs of maintenance of nuclear power plants stimulate the interest in different methods and approaches to optimize maintenance activities. Among different concepts, the Reliability Centered Maintenance (RCM) as an approach to improve Preventive Maintenance (PM) programmes is being widely discussed an applied in several IAEA Member States. In order to summarize basic principles and current implementation of the RCM, the IAEA organized a Consultants Meeting in November 1990. The report prepared during that meeting was discussed during the Technical Committee Meeting (TCM) held in May 1991. Numerous technical presentations as well as panel and plenary discussions took place at the TCM. This document contains the report of the Consultants Meeting (modified to include comments of the TCM), a summary of the most important discussions as well as all 14 papers presented at the TCM

  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. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

  3. National nuclear safety report 2004. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2004-01-01

    The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

  4. Developing safety culture in nuclear activities. Practical suggestions to assist progress

    International Nuclear Information System (INIS)

    2000-01-01

    The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by the IAEA as Safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

  5. Developing safety culture in nuclear activities. Practical suggestions to assist progress

    International Nuclear Information System (INIS)

    1998-01-01

    The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by IAEA as safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

  6. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

  7. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

  8. Model summary report for the safety assessment SR-Site

    International Nuclear Information System (INIS)

    Vahlund, Fredrik; Zetterstroem Evins, Lena; Lindgren, Maria

    2010-12-01

    This document is the model summary report for the safety assessment SR-Site. In the report, the quality assurance (QA) measures conducted for assessment codes are presented together with the chosen QA methodology. In the safety assessment project SR-Site, a large number of numerical models are used to analyse the system and to show compliance. In order to better understand how the different models interact and how information are transferred between the different models Assessment Model Flowcharts, AMFs, are used. From these, different modelling tasks can be identify and the computer codes used. As a large number of computer codes are used in the assessment the complexity of these differs to a large extent, some of the codes are commercial while others are developed especially for the assessment at hand. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined for all codes: - It must be demonstrated that the code is suitable for its purpose. - It must be demonstrated that the code has been properly used. - It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. - It must be described how data are transferred between the different computational tasks. Although the requirements are identical for all codes in the assessment, the measures used to show that the requirements are fulfilled will be different for different types of codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented together with a discussion on how the requirements are met

  9. Model summary report for the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Vahlund, Fredrik; Zetterstroem Evins, Lena (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Lindgren, Maria (Kemakta Konsult AB, Stockholm (Sweden))

    2010-12-15

    This document is the model summary report for the safety assessment SR-Site. In the report, the quality assurance (QA) measures conducted for assessment codes are presented together with the chosen QA methodology. In the safety assessment project SR-Site, a large number of numerical models are used to analyse the system and to show compliance. In order to better understand how the different models interact and how information are transferred between the different models Assessment Model Flowcharts, AMFs, are used. From these, different modelling tasks can be identify and the computer codes used. As a large number of computer codes are used in the assessment the complexity of these differs to a large extent, some of the codes are commercial while others are developed especially for the assessment at hand. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined for all codes: - It must be demonstrated that the code is suitable for its purpose. - It must be demonstrated that the code has been properly used. - It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. - It must be described how data are transferred between the different computational tasks. Although the requirements are identical for all codes in the assessment, the measures used to show that the requirements are fulfilled will be different for different types of codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented together with a discussion on how the requirements are met

  10. 75 FR 17167 - Sunshine Act Meetings; Correction

    Science.gov (United States)

    2010-04-05

    ... NATIONAL COUNCIL ON DISABILITY Sunshine Act Meetings; Correction AGENCY: National Council on Disability. ACTION: Notice; correction. Type: Quarterly meeting. SUMMARY: NCD published a Sunshine Act Meeting Notice in the Federal Register on March 11, 2010, notifying the public of a quarterly meeting in...

  11. Nuclear Safety Review 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

  12. Nuclear Safety Review 2013

    International Nuclear Information System (INIS)

    2013-07-01

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

  13. Summaries of poster contributions

    International Nuclear Information System (INIS)

    1981-01-01

    The 10. meeting covered subjects on the application of electron microscopy in numerous fields such as biology and medicine, solid state physics, semiconductor research and production, crystallography, materials science, and chemistry of polymers. 174 summaries of poster contributions are included

  14. National nuclear safety report 2005. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2006-01-01

    This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

  15. Nuclear data for production of therapeutic radionuclides. Summary report of second research coordination meeting

    International Nuclear Information System (INIS)

    Sublet, J.-Ch.; Capote Noy, R.

    2004-11-01

    A summary is given of the Second Research Coordination Meeting on Nuclear Data for Production of Therapeutic Radionuclides. The new library of evaluated cross section will cover the reactor and/or accelerator production of therapeutic radionuclides to appropriate specific activities and purity along with the relevant decay data. There are a significant number of radioisotopes in use or being proposed for therapeutic applications. As a consequence of the work undertaken during the course of this CRP, the resulting completeness and accuracy of the nuclear data for the production of these nuclides to appropriate specific activities and purity along with the re-definition of their decay data should be adequate for safe and efficient medical applications. The radioisotopes to be considered in the CRP were divided into two categories: Established Radioisotopes (therapeutic radioisotopes that have established clinical uses) and Emerging Radioisotopes (less-commonly used but potentially interesting radioisotopes for which medical applications have been demonstrated). Experimental data compilations and selection and preliminary evaluations for each of the reactions were extensively discussed during the meeting. The recommendations for both established and emerging radionuclides, and validation/testing of the cross section library are summarized. Technical discussions and the resulting work plan of the Coordinated Research Programme are summarized for every reaction path to be evaluated, along with actions and deadlines. Participants' contributions to the RCM are also attached. (author)

  16. Innovative nuclear reactor - Indian approach to meet user requirements for safety

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2002-01-01

    Full text: For sustainable development of nuclear energy, a number of key issues are to be addressed. It should be economically competitive; it must address the issues related to nuclear safety, proliferation resistance, environmental impact, waste disposal and cross cutting issues like social and infra-structural aspects. To compete successfully in the long term, in the highly competitive energy market and to overcome other challenges, it is necessary to introduce innovative reactor and fuel cycle concepts. Indian Advanced Heavy Water Reactor (AHWR) is one such innovative reactor. To guide the research and development activities related to innovative concepts, user requirements are to be formulated. User requirements covering various aspects of sustainable development are being formulated at both national and international levels. One such international project involved in the formulation of user requirements is the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). This paper deals with INPRO user requirements for safety and Indian approach to meet these requirements through AHWR

  17. Summary and Outlook for KEKTC5

    International Nuclear Information System (INIS)

    Quinn, Helen R

    2002-01-01

    This is the summary talk of a meeting held at the KEK, Tsukuba, Japan, November 20-22, 2001. This meeting has been a wonderful testimony to the success of particle physics in Japan. The hosts are involved in all aspects of flavor physics, both with the world-class facilities in this laboratory and elsewhere in this country, and through their participation in experiments elsewhere. The results they have shown these past few days are at the forefront of B physics and neutrino physics, and the plans for the future we have seen are equally impressive. I give a brief summary of the talks we heard, and a few comments of my own on various points that have been made. Other talks given at this meeting are referred to by the speakers last name; these talks will appear in the same proceedings. See these talks for the detailed references for each subject

  18. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

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

    International Nuclear Information System (INIS)

    1993-01-01

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

  20. 2nd IAEA research coordination meeting on collection and evaluation of reference data for thermo-mechanical properties of fusion reactor plasma facing materials. Summary report

    International Nuclear Information System (INIS)

    Langley, R.A.

    1996-08-01

    The proceedings and results of the 2nd IAEA Research Coordination Meeting on ''Collection and Evaluation of Reference Data for Thermo-mechanical Properties of Fusion Reactor Plasma Facing Materials'' held on March 25, 26 and 27, 1996 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of presentations made by the meeting participants, the results of discussions amongst the participants regarding the status of data, publication of a multi-author review paper and recommendations regarding future work. (author). 1 tab

  1. Establishment of an international reference data library of nuclear activation cross sections. Summary report of the first research co-ordination meeting held in Debrecen, Hungary, from 4 to 7 October 1994

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1995-02-01

    The report contains the Summary of the First IAEA Research Co-ordination Meeting (RCM) of the new Co-ordinated Research Programme (CRP) on ''Establishment of an International Reference Data Library of Nuclear Activation Cross Sections''. The meeting was organized by the IAEA Nuclear Data Section with co-operation and assistance of local organizers from the Institute of Experimental Physics and held in Debrecen, Hungary, from 4 to 7 October 1994. The purpose of the RCM was to discuss the scope and goals of the CRP, to report and evaluate the first results of the research carried out by each participating laboratory, to review the current tasks, identify further actions of participants and agree on the coordination of work under this CRP. The detailed agenda, the list of participants, conclusions and recommendations of the meeting are presented in the summary report. (author)

  2. 2017 Landsat Science Team Summer Meeting Summary

    Science.gov (United States)

    Crawford, Christopher J.; Loveland, Thomas R.; Wulder, Michael A.; Irons, James R.

    2018-01-01

    The summer meeting of the U.S. Geological Survey (USGS)-NASA Landsat Science Team (LST) was held June 11-13, 2017, at the USGS’s Earth Resources Observation and Science (EROS) Center near Sioux Falls, SD. This was the final meeting of the Second (2012-2017) LST.1 Frank Kelly [EROS—Center Director] welcomed the attendees and expressed his thanks to the LST members for their contributions. He then introduced video-recorded messages from South Dakota’s U.S. senators, John Thune and Mike Rounds, in which they acknowledged the efforts of the team in advancing the societal impacts of the Landsat Program.

  3. AER Working Group D on VVER safety analysis minutes of the meeting in Rez, Czech Republic 18-20 May 1998

    International Nuclear Information System (INIS)

    Siltanen, P.

    1998-01-01

    AER Working Group D on VVER reactor safety analysis held its seventh meeting in Hotel Vltava in Rez near Prague during the period 18-20 May 1998. There were altogether 11 participants from 8 member organisations. The coordinator for the working group, Mr. P. Siltanen (IVO) served as chairman. In addition to the general information exchange on recent activities, the topics of the meeting included: First review of solutions to the 3-dimensional AER Dynamic Benchmark Problem No. 5 on a steam line break accident. This benchmark involves a break of the main steam header. Safety analysis of reactivity events. Recent code development work and fuel behaviour. Coolant mixing calculations and experiments related to diluted slugs. A list of participants and a list of handouts distributed at the meeting are attached to the minutes. (author)

  4. 77 FR 22286 - Western Pacific Fishery Management Council; Public Meeting

    Science.gov (United States)

    2012-04-13

    ... Pacific Fishery Management Council; Public Meeting AGENCY: National Marine Fisheries Service (NMFS.... SUMMARY: The Western Pacific Fishery Management Council (Council) will hold a meeting of its Pelagics Plan... pelagics annual report module changes 4. American Samoa annual report module changes 5. Summary of current...

  5. Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

    International Nuclear Information System (INIS)

    1998-01-01

    The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

  6. Safety study application guide

    International Nuclear Information System (INIS)

    1993-07-01

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly open-quotes lowclose quotes) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, open-quotes Technical Safety Requirements,close quotes and 5480.23, open-quotes Nuclear Safety Analysis Reports.close quotes A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis

  7. Specialists' meeting on carbon in sodium. Summary report

    International Nuclear Information System (INIS)

    1980-05-01

    The purpose of the meeting was to provide a forum for the exchange of views on: the chemistry and thermodynamics of carbon in sodium; the analysis and monitoring of carbon in sodium; the behaviour of carbon in sodium circuits; and the implications of the above in LMFBRs. The technical parts of the meeting were divided into five major sessions

  8. Specialists' meeting on carbon in sodium. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-05-01

    The purpose of the meeting was to provide a forum for the exchange of views on: the chemistry and thermodynamics of carbon in sodium; the analysis and monitoring of carbon in sodium; the behaviour of carbon in sodium circuits; and the implications of the above in LMFBRs. The technical parts of the meeting were divided into five major sessions.

  9. 75 FR 59747 - NASA Advisory Council; Meeting.

    Science.gov (United States)

    2010-09-28

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: (10-113)] NASA Advisory Council; Meeting. AGENCY: National Aeronautics and Space Administration. ACTION: Notice of meeting. SUMMARY: In accordance... Space Administration announces a meeting of the NASA Advisory Council. DATES: Wednesday, October 6, 2010...

  10. 75 FR 13134 - Notice of Meeting

    Science.gov (United States)

    2010-03-18

    ...)(6). Grant applications for the Medical Liability and Safety Innovation Projects (R21) applications... disclosure under the above- cited statutes. SEP Meeting on: Medical Liability and Safety Innovation Projects... meeting) Place: Doubletree Bethesda Hotel & Executive Meeting Center, 8120 Wisconsin Avenue, Conference...

  11. ACRF Archive User Meeting Summary

    Energy Technology Data Exchange (ETDEWEB)

    SA Edgerton; RA McCord; DP Kaiser

    2007-10-30

    On October 30, 2007, the U.S. Department of Energy’s (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) sponsored an all-day workshop to assess the status of the ACRF Archive. Focus areas included usability of current functions, plans for revised functions, proposals for new functions, and an overarching discussion of new ideas. Although 13 scientists familiar with ACRF and the ARM Program were invited to the workshop, only 10 scientists were available to attend the workshop. ACRF consists of the infrastructure that was developed to support the ARM Program and includes the ACRF Archive (previously called the ARM Archive). The scientists who participated in the meeting ranged from those who used the Archive frequently to those who seldom or never had accessed the Archive. The group was spread across disciplines, i.e. modelers, conservationists, and others from universities and government laboratories. A few of the participants were funded by the ARM Program, but most were not funded currently by ARM. During the past year, several improvements were made to the ACRF Archive to link it with the ARM/ACRF web pages, add a shopping cart feature, and expand on search parameters. Additional modifications have been proposed and prototypes of these proposals were made available for the participants. The participants were given several exercises to do before the meeting, and their feedback was requested to help identify potential problems and shortcomings with the existing structure and to recommend improvements.

  12. Summary Record of the First Meeting of the Radioactive Waste Repository Metadata Management (RepMet) Initiative

    International Nuclear Information System (INIS)

    2014-01-01

    National radioactive waste repository programmes are collecting large amounts of data to support the long-term management of their nations' radioactive wastes. The data and related records increase in number, type and quality as programmes proceed through the successive stages of repository development: pre-siting, siting, characterisation, construction, operation and finally closure. Regulatory and societal approvals are included in this sequence. Some programmes are also documenting past repository projects and facing a challenge in allowing both current and future generations to understand actions carried out in the past. Metadata allows context to be stored with data and information so that it can be located, used, updated and maintained. Metadata helps waste management organisations better utilise their data in carrying out their statutory tasks and can also help verify and demonstrate that their programmes are appropriately driven. The NEA Radioactive Waste Repository Metadata Management (RepMet) initiative aims to bring about a better understanding of the identification and administration of metadata - a key aspect of data management - to support national programmes in managing their radioactive waste repository data, information and records in a way that is both harmonised internationally and suitable for long-term management and use. This is a summary record of the 1. meeting of the RepMet initiative. The actions and decisions from this meeting were sent separately to the group after the meeting, but are also included in this document (Annex A). The list of participants is attached as well (Annex B)

  13. Compendium of computer codes for the safety analysis of LMFBR's

    International Nuclear Information System (INIS)

    1975-06-01

    A high level of mathematical sophistication is required in the safety analysis of LMFBR's to adequately meet the demands for realism and confidence in all areas of accident consequence evaluation. The numerical solution procedures associated with these analyses are generally so complex and time consuming as to necessitate their programming into computer codes. These computer codes have become extremely powerful tools for safety analysis, combining unique advantages in accuracy, speed and cost. The number, diversity and complexity of LMFBR safety codes in the U. S. has grown rapidly in recent years. It is estimated that over 100 such codes exist in various stages of development throughout the country. It is inevitable that such a large assortment of codes will require rigorous cataloguing and abstracting to aid individuals in identifying what is available. It is the purpose of this compendium to provide such a service through the compilation of code summaries which describe and clarify the status of domestic LMFBR safety codes. (U.S.)

  14. Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

    International Nuclear Information System (INIS)

    2014-01-01

    The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-10) in Okinawa, Japan is sponsored by Atomic Energy Society of Japan, in cooperation with the International Atomic Energy Agency, and co-sponsored by American Nuclear Society Thermal Hydraulics Division among others. Enhanced safety and reducing cost are going together, which can be achieved through continued research and development efforts. NUTHOS keeps you abreast of the most updated information in the advancement of science and technology in nuclear thermal hydraulics, operations and safety, and provides you insights into the future. (J.P.N.)

  15. 75 FR 13135 - Notice of Meeting

    Science.gov (United States)

    2010-03-18

    ...). Grant applications for the Medical Liability and Safety Demonstration Projects (R18) applications are to... disclosure under the above-cited statutes. SEP Meeting on: Medical Liability and Safety Demonstration... remainder of the meeting). Place: Doubletree Bethesda Hotel & Executive Meeting Center, 8120 Wisconsin...

  16. HTGR Dust Safety Issues and Needs for Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    Paul W. Humrickhouse

    2011-06-01

    This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety. It reflects the work and input of approximately 40 participants from the U.S. Department of Energy and its National Labs, the U.S. Nuclear Regulatory Commission, industry, academia, and international nuclear research organizations on the topics of dust generation and characterization, transport, fission product interactions, and chemical reactions. The meeting was organized by the Idaho National Laboratory under the auspices of the Next Generation Nuclear Plant Project, with support from the U.S. Nuclear Regulatory Commission. Information gleaned from the report and related meetings will be used to enhance the fuel, graphite, and methods technical program plans that guide research and development under the Next Generation Nuclear Plant Project. Based on meeting discussions and presentations, major research and development needs include: generating adsorption isotherms for fission products that display an affinity for dust, investigating the formation and properties of carbonaceous crust on the inside of high temperature reactor coolant pipes, and confirming the predominant source of dust as abrasion between fuel spheres and the fuel handling system.

  17. Special Issue. 5th Meeting on Technology and Safety

    International Nuclear Information System (INIS)

    Kusakabe, Masashi; Kumagaya, Tadafusa; Minohara, Shinichi

    2010-01-01

    The documents in this Special Issue are the representative reports of achievements presented in the National Institute of Radiological Sciences (NIRS) 5th Meeting on Technology and Safety held on March 17, 2010. Personnel and investigators of NIRS and related companies gave their achievements by 19 oral and 31 poster presentations in fields of [IAR] irradiation (2 topics), accelerator/radiometry (9 topics), [EA] experimental animals (25 topics), [SM] safety management of facilities (5 topics), computer network system (4 topics), experimental instrument (1 topic), molecular imaging (2 topics) and others (2 topics). The Issue contains, as well as introductory and ending remarks, following 12 topics: [IAR] Working report of patient positioning system for radiotherapy with use of X-ray flat panel detector; Status of maintenance and management of facilities and equipments in Research center for Radiation Emergency Medicine; [EA] Past, present and future of mouse breeding in NIRS; Breeding of marmoset in NIRS/How can we have a bouncing marmoset baby?; Establishment of a genotyping method of transformed genes in transgenic mouse/genome walking method; Genetic monitoring system of mice by micro-satellite marker and its application in NIRS; Verification of sorting precision of FACSAria (Becton Dickinson and Co.), a highly sensitive, rapid sorting apparatus of cells/for precise sorting; Proposal of a task-solution workflow to determine the animal features for molecular imaging studies; [SM] Toward the introduction of Occupational Safety and Health Management System in NIRS; Use of unsealed radioisotopes less than the lower limit outside the legal control area; Arrangement of managing and supporting system for clinical studies; and Rearrangement of working system of personnel affairs. (T.T.)

  18. Public meetings

    CERN Multimedia

    Staff Association

    2014-01-01

    You were hundreds of persons to participate in our information meetings of October 3 and 6 2014, and we thank you for your participation! The full presentation is available here. A summary of the topics is available here (in french).

  19. 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

  20. Discussing compliance. Summary report from discussions with Robert Bernero and Chris Whipple regarding compliance with the Swedish HLW Regulations from meetings in Stockholm May 3 and 4, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, Mikael

    1999-06-01

    Summary report from discussions with Robert Bernero and Chris Whipple regarding compliance with the Swedish HLW Regulations from meetings in Stockholm. The report also contains bibliographical information and preliminary observations made by Robert Bernero and Chris Whipple.

  1. Discussing compliance. Summary report from discussions with Robert Bernero and Chris Whipple regarding compliance with the Swedish HLW Regulations from meetings in Stockholm May 3 and 4, 1999

    International Nuclear Information System (INIS)

    Jensen, Mikael

    1999-06-01

    Summary report from discussions with Robert Bernero and Chris Whipple regarding compliance with the Swedish HLW Regulations from meetings in Stockholm. The report also contains bibliographical information and preliminary observations made by Robert Bernero and Chris Whipple

  2. 'AER working group D on VVER safety analysis' minutes of the meeting in Rossendorf, Germany, 10-12 May 1999

    International Nuclear Information System (INIS)

    Siltanen, P.

    1999-01-01

    AER Working Group D on VVER reactor safety analysis held its eighth meeting in Research Centre Rossendorf during the period 10-12 May 1999. There were altogether 14 participants from eight member organizations. In addition to the general information exchange on recent activities, the topics of the meeting included: Final conclusions and lessons from the solution of the AER Dynamic Benchmark Problem No. 5 on a main steam header break accident; Validation of dynamics codes and the definition of a 6th dynamic benchmark; Safety analyses and reactivity issues: approaches and results; Advances in development of models and codes for reactor dynamics applications; Documentation of dynamic benchmark problems and solutions for the AER Benchmark Book; Future activities. (author)

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

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-12-01

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

  4. 76 FR 20375 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-04-12

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities ACTION: Notice of additional meeting. SUMMARY: Pursuant to the... the following meeting of the Humanities Panel will be held at the Old Post Office, 1100 Pennsylvania...

  5. 76 FR 70168 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-11-10

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of additional meeting. SUMMARY: Pursuant to the... the following meeting of the Humanities Panel will be held at the Old Post Office, 1100 Pennsylvania...

  6. 76 FR 41826 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-07-15

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of additional meeting. SUMMARY: Pursuant to the... the following meeting of the Humanities Panel will be held at the Old Post Office, 1100 Pennsylvania...

  7. 78 FR 61404 - Federal Salary Council; Meeting

    Science.gov (United States)

    2013-10-03

    ... OFFICE OF PERSONNEL MANAGEMENT Federal Salary Council; Meeting AGENCY: Office of Personnel Management. ACTION: Notice of meeting. SUMMARY: The Federal Salary Council will meet on November 5, 2013, at... recommendations cover the establishment or modification of locality pay areas, the coverage of salary surveys, the...

  8. 75 FR 63215 - Federal Salary Council Meeting

    Science.gov (United States)

    2010-10-14

    ... OFFICE OF PERSONNEL MANAGEMENT Federal Salary Council Meeting AGENCY: Office of Personnel Management. ACTION: Notice of Meeting. SUMMARY: The Federal Salary Council will meet on October 29, 2010, at... recommendations cover the establishment or modification of locality pay areas, the coverage of salary surveys, the...

  9. 76 FR 59175 - Federal Salary Council; Meeting

    Science.gov (United States)

    2011-09-23

    ... OFFICE OF PERSONNEL MANAGEMENT Federal Salary Council; Meeting AGENCY: Office of Personnel Management. ACTION: Notice of meeting. SUMMARY: The Federal Salary Council will meet on November 4, 2011, at... recommendations cover the establishment or modification of locality pay areas, the coverage of salary surveys, the...

  10. France - Convention on nuclear safety. Fourth national report established in view of the 2008 examination meeting

    International Nuclear Information System (INIS)

    2007-07-01

    This report is the fourth one established in compliance with the article 5 of the international Convention on nuclear safety, and presents measures implemented by France to meet each of the Convention requirements. It addresses electro-nuclear reactors as well as research reactors. After an overview of the main evolutions since the third French report, and a general presentation of the French national nuclear policy, the report addresses the different articles of the Convention. These articles deal with general arrangements (application arrangements, presentation of reports, existing nuclear installations with their safety assessments and main safety improvements brought to the different nuclear reactors), law and regulation (legal and regulatory framework, regulation bodies, responsibility of an authorization holder), general safety considerations (priority for safety, human and financial resources, human factors, quality insurance, safety assessment and verification, radiation protection, organisation in case of emergency), and installation safety (site selection, design and construction, exploitation, activities planned to improve safety). Appendices propose a list and locations of French nuclear reactors, a list of the main legal and regulatory texts, presentations of nuclear reactor operators (EDF, CEA, ILL), and an overview of practices of control of the environment

  11. SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

    International Nuclear Information System (INIS)

    Puska, E.

    2006-12-01

    Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

  12. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

  13. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting

  14. Plutonium focus area: Technology summary

    International Nuclear Information System (INIS)

    1996-03-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this approach, EM developed a management structure and principles that led to creation of specific focus areas. These organizations were designed to focus scientific and technical talent throughout DOE and the national scientific community on major environmental restoration and waste management problems facing DOE. The focus area approach provides the framework for inter-site cooperation and leveraging of resources on common problems. After the original establishment of five major focus areas within the Office of Technology Development (EM-50), the Nuclear Materials Stabilization Task Group (NMSTG, EM-66) followed EM-50's structure and chartered the Plutonium Focus Area (PFA). NMSTG's charter to the PFA, described in detail later in this book, plays a major role in meeting the EM-66 commitments to the Defense Nuclear Facilities Safety Board (DNFSB). The PFA is a new program for FY96 and as such, the primary focus of revision 0 of this Technology Summary is an introduction to the Focus Area; its history, development, and management structure, including summaries of selected technologies being developed. Revision 1 to the Plutonium Focus Area Technology Summary is slated to include details on all technologies being developed, and is currently planned for release in August 1996. The following report outlines the scope and mission of the Office of Environmental Management, EM-60, and EM-66 organizations as related to the PFA organizational structure

  15. Assessment of nuclear data needs for particle induced gamma ray emission (PIGE). Summary report of consultants' meeting

    International Nuclear Information System (INIS)

    Abriola, D.; Pedro de Jesus, A.

    2010-03-01

    A summary is given of a Consultants' Meeting assembled to assess the viability of a new IAEA Co-ordinated Research Project (CRP) on Development of nuclear data for PIGE for analytical applications. The need for such a CRP was strongly agreed. Both the technical discussions and the expected outcomes of such a project are described, along with detailed recommendations for implementation. The participants discussed the past and present status of the field and the experiments performed in their home institutes. Subsequently, they addressed the nuclear data needs for PIGE analysis and produced recommendations concerning the compilation, assessment, measurements, evaluation and benchmarking of cross-section data for PIGE as well as their inclusion in the existent IBANDL database. (author)

  16. Proceedings of the specialist meeting on the safety of water reactors fuel elements

    International Nuclear Information System (INIS)

    1973-01-01

    This specialist meeting on the safety of water reactors fuel elements was held in Saclay (France) in October 1973, and was organized by CSNI and CEA. It attracted specialists from 14 countries. Session I was devoted to normal operating conditions (coolant-cladding and fuel-cladding interactions, fission product release, effects of cladding deformation on fuel element performances and reactor operating limits); Session II was devoted to operating reactor accidents and failures, anomalous transients and handling accidents; Session III was devoted to modifications to be applied to fuel elements in order to enhance their safety and reliability; Session IV was devoted to Loss-of-Coolant Accidents (LOCA)(cladding behaviour during the accident, assembly behaviour during the accident, criteria to be considered for the study of fuel element behaviour during a LOCA)

  17. 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

  18. Nuclear Safety Review for 2015

    International Nuclear Information System (INIS)

    2015-06-01

    The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

  19. 76 FR 6828 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-02-08

    ... THE NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of Meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  20. 75 FR 18906 - Meetings of Humanities Panel

    Science.gov (United States)

    2010-04-13

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of Meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  1. 75 FR 50007 - Meetings of Humanities Panel

    Science.gov (United States)

    2010-08-16

    ... THE NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of Meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  2. 75 FR 26285 - Meetings of Humanities Panel

    Science.gov (United States)

    2010-05-11

    ... THE NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  3. 77 FR 22359 - Meetings of Humanities Panel

    Science.gov (United States)

    2012-04-13

    ... THE NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of Meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue NW...

  4. 76 FR 52697 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-08-23

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  5. 76 FR 63664 - Meetings of Humanities Panel

    Science.gov (United States)

    2011-10-13

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: The National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to the provisions of... following meetings of Humanities Panels will be held at the Old Post Office, 1100 Pennsylvania Avenue, NW...

  6. Model summary report for the safety assessment SFR 1 SAR-08

    Energy Technology Data Exchange (ETDEWEB)

    2008-03-15

    This document is the model summary report for the safety assessment SFR 1 SAR-08. In the report, the quality assurance measures conducted for the assessment codes are presented together with the chosen methodology. In the safety assessment SFR1 SAR-08, a number of different computer codes are used. In order to better understand how these codes are related an Assessment Model Flowchart, AMF, has been produced within the project. From the AMF, it is possible to identify the different modelling tasks and consequently also the different computer codes used. A number of different computer codes are used in the assessment of which some are commercial while others are developed for assessment projects. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined: - It must be demonstrated that the code is suitable for its purpose. - It must be demonstrated that the code has been properly used. - It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. Although the requirements are identical for all codes, the measures used to show that the requirements are fulfilled will be different for different codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented and it is shown how the requirements are met

  7. Model summary report for the safety assessment SFR 1 SAR-08

    International Nuclear Information System (INIS)

    2008-03-01

    This document is the model summary report for the safety assessment SFR 1 SAR-08. In the report, the quality assurance measures conducted for the assessment codes are presented together with the chosen methodology. In the safety assessment SFR1 SAR-08, a number of different computer codes are used. In order to better understand how these codes are related an Assessment Model Flowchart, AMF, has been produced within the project. From the AMF, it is possible to identify the different modelling tasks and consequently also the different computer codes used. A number of different computer codes are used in the assessment of which some are commercial while others are developed for assessment projects. QA requirements must on the one hand take this diversity into account and on the other hand be well defined. In the methodology section of the report the following requirements are defined: - It must be demonstrated that the code is suitable for its purpose. - It must be demonstrated that the code has been properly used. - It must be demonstrated that the code development process has followed appropriate procedures and that the code produces accurate results. Although the requirements are identical for all codes, the measures used to show that the requirements are fulfilled will be different for different codes (for instance due to the fact that for some software the source-code is not available for review). Subsequent to the methodology section, each assessment code is presented and it is shown how the requirements are met

  8. International Working Group on Fast Reactors Second Annual Meeting. Summary Report

    International Nuclear Information System (INIS)

    1969-01-01

    The Agenda of the Meeting was as follows: Opening of the meeting. 2. Appraisal of the IWGFB's activity for the period from the first annual meeting of the Group. 3. Comments on national programmes on fast breeder reactors. 4. Presentation of general findings and conclusions of national and regional meetings on fast reactor problems held in represented countries and international organisations last year. 5. Comments on the programmes of international meetings on fast reactors to be held in 1969. 6. Consideration of a schedule for meetings on fast reactors in 1970. 7. Suggestions for the topics and location of specialists' meetings in 1969-1970. 8. Suggestions for reviews and studies in the field of fast reactors. 9. The time and place of the third annual meeting of the IWGFR. 10. Closing of the meeting

  9. 77 FR 67808 - Environmental Management Advisory Board Meeting

    Science.gov (United States)

    2012-11-14

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board Meeting AGENCY: Department of Energy. ACTION: Notice of Open Meeting. SUMMARY: This notice announces a meeting of the Environmental Management... Assistant Secretary for Environmental Management (EM) with advice and recommendations on corporate issues...

  10. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  11. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  12. 78 FR 63501 - Meetings of Humanities Panel

    Science.gov (United States)

    2013-10-24

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the... Humanities Panel will be held during November, 2013 as follows. The purpose of the meetings is for panel...

  13. 77 FR 61643 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-10-10

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... hereby given that sixteen meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  14. 78 FR 17942 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2013-03-25

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meetings. SUMMARY... hereby given that five meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  15. 78 FR 21978 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2013-04-12

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... is hereby given that one meeting of the Arts Advisory Panel to the National Council on the Arts will...

  16. 77 FR 67836 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-11-14

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of Meeting. SUMMARY... hereby given that fifteen meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  17. 77 FR 75672 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-12-21

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of Meeting. SUMMARY... hereby given that seven meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  18. 77 FR 41808 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-07-16

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... hereby given that two meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  19. 78 FR 68099 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2013-11-13

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of Meeting. SUMMARY... hereby given that twenty- one meetings of the Arts Advisory Panel to the National Council on the Arts...

  20. 77 FR 56875 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-09-14

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... hereby given that two meetings of the Arts Advisory Panel to the National Council on the Arts will be...

  1. Atomic and Molecular Data for State-Resolved Modelling of Hydrogen and Helium and Their Isotopes in Fusion Plasma. Summary Report of the First Research Coordination Meeting

    International Nuclear Information System (INIS)

    Braams, B. J.

    2013-12-01

    The First Research Coordination Meeting of the IAEA Coordinated Research Project (CRP) on 'Atomic and Molecular Data for State-Resolved Modelling of Hydrogen and Helium and Their Isotopes in Fusion Plasma' was held 10-12 August 2011 at IAEA Headquarters in Vienna. Participants reviewed the status of the database on molecular processes of H and He, identified data needs and made plans for development of new data in connection with the CRP. The proceedings of the meeting are summarized here. Participants' summaries and work plans are also provided. (author)

  2. 25. Meeting of the NEA NSC Working Party on International Nuclear Data Evaluation Co-operation (WPEC) - Summary Record (23-24 May 2013, NEA Headquarters, Issy-les-Moulineaux, France) - NEA-SEN-NSC-WPEC--2013-2

    International Nuclear Information System (INIS)

    Dupont, Emmeric

    2014-01-01

    This document summarized the content of the previous WPEC meeting held on 23-24 May 2013 at the NEA Headquarters. Experimental nuclear data activities of relevance to the evaluation projects were reviewed. Detailed information about the experimental activities is given in the reports and view graphs presented at the meeting (list in Annex 2). Progress in the major nuclear data evaluation projects was presented. Detailed information about the status of the evaluated nuclear data libraries is also given in the reports and view graphs presented at the meeting (see Annex 2). Results and conclusions of completed or near-completed subgroups were discussed. A summary table of all subgroup status is given in Annex 3. Activities of ongoing subgroups were presented. A summary table of all subgroup status is also given in Annex 3. Two new subgroup proposals were reviewed by WPEC. Detailed information about these proposals is given in the documents and view graphs presented at the meeting (list in Annex 2). Other points discussed at the 25. Meeting: presentation of the main WPEC objectives and working methods; Renewal of the WPEC mandate for the period 2013-2016; Conferences and meetings of interest to the nuclear data community; Time and place of next meeting

  3. Consultants' Meeting on Review Benchmarking of Nuclear Data for the Th/U Fuel Cycle. Summary Report

    International Nuclear Information System (INIS)

    Capote Noy, R.

    2011-02-01

    A summary is given of the Consultants' Meeting (CM) on Review and Benchmarking of Nuclear Data for the Th/U Fuel Cycle. An IAEA Coordinated Research Project (CRP) on 'Nuclear Data for Th/U Fuel Cycle' was concluded in 2005. The CRP activities resulted in new evaluated nuclear data files for 232 Th, 231 , 233 Pa (later adopted for the ENDF/B-VII.0 library) and improvements to existing evaluations for 232 , 233 , 234 , 236 U. Available nuclear data evaluations for 230 - 232 Th, 231,233 Pa and 232 , 233 , 234 U were reviewed including ROSFOND2010, CENDL-3.1, JENDL-4, JEFF-3.1.1, MINSKACT, and ENDF/B-VII.0 libraries. Benchmark results of available evaluations for 232 Th and 233 U were also discussed. (author)

  4. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  5. The International Technical Safety Forum

    CERN Multimedia

    CERN Bulletin

    2010-01-01

    The International Technical Safety Forum is a meeting of safety experts from several physics labs in Europe and the US. Since 1998 participants have been meeting every couple of years to discuss common challenges in safety matters. The Forum helps them define best practices and learn from the important lessons learned by others.   The Forum's participants in front of building 40. This year, the meeting took place at CERN from 12 to 16 April. “This year's meeting covered subjects ranging from communication and training in matters of safety, to cryogenic safety, emergency preparedness and risk analysis”, explains Ralf Trant, head of the CERN Safety Commission and organiser of this year’s Forum. Radiation protection issues are not discussed at the meeting since they involve different expertise. The goal of the Forum is to allow participants to share experience, learn lessons and acquire specific knowledge in a very open way. Round-table discussions, dedicated time for ...

  6. 75 FR 9885 - Environmental Management Advisory Board Meeting

    Science.gov (United States)

    2010-03-04

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board Meeting AGENCY: Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Environmental Management... purpose of EMAB is to provide the Assistant Secretary for Environmental Management (EM) with advice and...

  7. 76 FR 31319 - Environmental Management Advisory Board Meeting

    Science.gov (United States)

    2011-05-31

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board Meeting AGENCY: Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Environmental Management... purpose of EMAB is to provide the Assistant Secretary for Environmental Management (EM) with advice and...

  8. 76 FR 71959 - Environmental Management Advisory Board Meeting

    Science.gov (United States)

    2011-11-21

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board Meeting AGENCY: Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Environmental Management... of EMAB is to provide the Assistant Secretary for Environmental Management (EM) with advice and...

  9. 76 FR 5364 - Environmental Management Advisory Board Meeting

    Science.gov (United States)

    2011-01-31

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board Meeting AGENCY: Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Environmental Management... Board: The purpose of EMAB is to provide the Assistant Secretary for Environmental Management (EM) with...

  10. 76 FR 23798 - Nuclear Energy Advisory Committee; Meeting

    Science.gov (United States)

    2011-04-28

    ... DEPARTMENT OF ENERGY Nuclear Energy Advisory Committee; Meeting AGENCY: Office of Nuclear Energy, Department of Energy. ACTION: Notice of open meeting. SUMMARY: This notice announces a meeting of the Nuclear... [email protected]nuclear.energy.gov . SUPPLEMENTARY INFORMATION: Background: The Nuclear Energy Advisory...

  11. International review on safety requirements for the prototype fast breeder reactor “Monju”

    International Nuclear Information System (INIS)

    2016-01-01

    In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

  12. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

    International Nuclear Information System (INIS)

    1996-08-01

    Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

  13. 77 FR 48552 - Meetings of Humanities Panel

    Science.gov (United States)

    2012-08-14

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the Federal Advisory Committee Act (5 U.S.C. App.), notice is hereby given that 10 meetings of the Humanities...

  14. 78 FR 74175 - Meetings of Humanities Panel

    Science.gov (United States)

    2013-12-10

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the... Humanities Panel will be held during January 2014 as follows. The purpose of the meetings is for panel review...

  15. 78 FR 49550 - Meetings of Humanities Panel

    Science.gov (United States)

    2013-08-14

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the Federal Advisory Committee Act (5 U.S.C. App.), notice is hereby given that 11 meetings of the Humanities...

  16. 77 FR 75198 - Meetings of Humanities Panel

    Science.gov (United States)

    2012-12-19

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Meetings of Humanities Panel AGENCY: National Endowment for the Humanities. ACTION: Notice of meetings. SUMMARY: Pursuant to section 10(a)(2) of the Federal Advisory Committee Act (5 U.S.C. App.), notice is hereby given that 4 meetings of the Humanities...

  17. 75 FR 40850 - Notice of Public Meeting

    Science.gov (United States)

    2010-07-14

    ... meeting may end early if all business is completed. If the meeting date and location are changed due to... Membership 10. Old Business a. Denali Subsistence Management Plan b. Subsistence Uses of Horns, Antlers... Subsistence Resource Commission (SRC) program. SUMMARY: The Denali National Park SRC plans to meet to develop...

  18. 78 FR 42982 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2013-07-18

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of Meetings SUMMARY... hereby given one meeting of the Arts Advisory Panel to the National Council on the Arts will be held at...

  19. 78 FR 59978 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2013-09-30

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... hereby given that one meeting of the Arts Advisory Panel to the National Council on the Arts will be held...

  20. 77 FR 49026 - Arts Advisory Panel Meeting

    Science.gov (United States)

    2012-08-15

    ... NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES Arts Advisory Panel Meeting AGENCY: National Endowment for the Arts, National Foundation on the Arts and Humanities. ACTION: Notice of meeting. SUMMARY... hereby given that one meeting of the Arts Advisory Panel to the National Council on the Arts will be held...