WorldWideScience

Sample records for technical operations committee

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

    International Nuclear Information System (INIS)

    2000-10-01

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

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

    International Nuclear Information System (INIS)

    2000-10-01

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

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

    International Nuclear Information System (INIS)

    2001-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

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

  5. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

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

  6. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    2001-01-01

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

  7. ITER technical advisory committee meeting at Garching

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Engelmann, F.

    2000-01-01

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

  9. Update of technical coordinating committee activities

    International Nuclear Information System (INIS)

    Alvarado, R.A.

    1995-01-01

    The Technical Coordinating Committee has its origins in the earliest days of implementing the Low-Level Radioactive Waste Policy Act. Between 1982 and 1985, individuals in several of the states felt that coordination among the states would be beneficial to all by affording states a cost-effective method for sharing ideas, discussing alternatives, and presenting solutions to common problems. At the current time, the committee comprises members from each of the sited states. Various compacts, federal agencies, and industry groups participate in committee activities. The Low-Level Management Program provides support for the committee through the provision of logistical support and limited manpower allocation. Activities of the committee have recently focused on waste treatment and minimization technologies. The committee also has worked diligently to see the review of the 3RSTAT computer code completed. The committee has taken a position on various regulatory proposals the past year. The committee expects to continue its work until new sites are brought online

  10. Update of technical coordinating committee activities

    Energy Technology Data Exchange (ETDEWEB)

    Alvarado, R.A.

    1995-12-31

    The Technical Coordinating Committee has its origins in the earliest days of implementing the Low-Level Radioactive Waste Policy Act. Between 1982 and 1985, individuals in several of the states felt that coordination among the states would be beneficial to all by affording states a cost-effective method for sharing ideas, discussing alternatives, and presenting solutions to common problems. At the current time, the committee comprises members from each of the sited states. Various compacts, federal agencies, and industry groups participate in committee activities. The Low-Level Management Program provides support for the committee through the provision of logistical support and limited manpower allocation. Activities of the committee have recently focused on waste treatment and minimization technologies. The committee also has worked diligently to see the review of the 3RSTAT computer code completed. The committee has taken a position on various regulatory proposals the past year. The committee expects to continue its work until new sites are brought online.

  11. Human research ethics committees in technical universities.

    Science.gov (United States)

    Koepsell, David; Brinkman, Willem-Paul; Pont, Sylvia

    2014-07-01

    Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although mandated in the United States, the United Kingdom, Canada, and Australia, non-medical research involving humans need not receive ethics review in much of Europe, Asia, Latin America, and Africa. Our survey of the top 50 technical universities in the world shows that, where not specifically mandated by law, most technical universities do not employ ethics committees to review human studies. As the domains of basic and applied sciences expand, ethics committees are increasingly needed to guide and oversee all such research regardless of legal requirements. We offer as examples, from our experience as an ethics committee in a major European technical university, ways in which such a committee provides needed services and can help ensure more ethical studies involving humans outside the standard medical context. We provide some arguments for creating such committees, and in our supplemental article, we provide specific examples of cases and concerns that may confront technical, engineering, and design research, as well as outline the general framework we have used in creating our committee. © The Author(s) 2014.

  12. The ESO Scientific and Technical Committee.

    Science.gov (United States)

    Léna, P.

    1982-03-01

    Since 1978, the structure of ESO involves a Scientific and Technical Committee (STC) which advises the Council on scientific and technical matters. This committee meets twice a year, usually at Garehing; its members are nominated by the Council and their term is 4 years. The STC has 10 members, who are as evenly distributed as possible among member countries, although indeed mainly chosen for their scientific abilities. The chairman is invited to attend Council meetings and to report to the members.

  13. 77 FR 42298 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-07-18

    ... Biomass Research and Development Technical Advisory Committee (Technical Advisory Committee). DATES: The... 9008(d) established the Biomass Research and Development Technical Advisory Committee and lays forth... nomination. Appointments to the Biomass Research and Development Technical Advisory Committee will be made by...

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

    International Nuclear Information System (INIS)

    Latge, C.

    1997-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-11-01

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

  16. 76 FR 36102 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-06-21

    ... vacancies on the Biomass Research and Development Technical Advisory Committee (Technical Advisory Committee..., 2008, H.R. 6124]. FCEA section 9008(d) establishes the Biomass Research and Development Technical... committee are ineligible for nomination. Appointments to the Biomass Research and Development Technical...

  17. Drafting & Design Technology. Technical Committee Report.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This Technical Committee Report prepared by industry representatives in Idaho lists the skills currently necessary for an employee in that state to obtain a job in drafting and design technology, retain a job once hired, and advance in that occupational field. (Task lists are grouped according to duty areas generally used in industry settings, and…

  18. Applied Welding Technology. Technical Committee Report.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This Technical Committee Report prepared by industry representatives in Idaho lists the skills currently necessary for an employee in that state to obtain a job in applied welding technology, retain a job once hired, and advance in that occupational field. (Task lists are grouped according to duty areas generally used in industry settings, and are…

  19. Human Research Ethics Committees in Technical Universities

    NARCIS (Netherlands)

    Koepsell, D.R.; Brinkman, W.P.; Pont, S.C.

    2014-01-01

    Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although

  20. State Technical Committee for Accounting. Official Report.

    Science.gov (United States)

    Jensen, Claudia

    This report contains validated task inventory listings for accounting occupations. An introductory report in brief outline form gives background of the work of the technical committee that identified the duties and tasks. This is followed by four attachments which make up most of the document. Attachment A has two parts: (1) an accounting skills…

  1. 77 FR 20377 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-04-04

    ... Biomass Research and Development Technical Advisory Committee under Section 9008(d) of the Food... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Office of Energy Efficiency and Renewable Energy, Department...

  2. 75 FR 20817 - Information Systems Technical Advisory Committee

    Science.gov (United States)

    2010-04-21

    ... equipment and technology. Wednesday, May 5 Public Session 1. Welcome and Introduction. 2. Working Group... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC...

  3. 77 FR 64464 - Information Systems Technical Advisory Committee

    Science.gov (United States)

    2012-10-22

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, November 7...

  4. 78 FR 64932 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-10-30

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy... announces an open meeting of the Biomass Research and Development Technical Advisory Committee under Section... Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral...

  5. Technologies for improving current and future light water reactor operation and maintenance: Development on the basis of experience. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-09-01

    experienced in nuclear power plant operation and maintenance. Worldwide, the average energy availability factor has increased from approximately 70 percent in 1989 to 79 percent' in 1998, with some utilities achieving significantly higher values. This is being achieved through integrated programmes, including personnel training and quality assurance, from improvements implemented in plant systems and components, and from improvements in outage duration for maintenance, refuelling, and other scheduled shutdowns, as well as forced outages. International co-operation is a key role in this success. The various programmes of the World Association of Nuclear Operators (WANO) to exchange information and encourage communication of experience, and the activities of the IAEA including projects in nuclear power plant performance assessment and feedback, effective quality management, and information exchange meetings on technology advances, are important examples of international co-operation to improve the performance of nuclear power plants. This IAEA Technical Committee meeting (TCM) was convened to provide a forum for information exchange on technologies for improving plant operation and maintenance which can contribute to enhanced economic competitiveness of LWRs, and on on-going or planned technology development expected to achieve further improvements. Information exchange of recent positive experience on development and/or implementation of technologies that have resulted in reduced operation and maintenance costs of LWRs, and information on on-going or planned activities, was strongly encouraged

  6. Technologies for improving current and future light water reactor operation and maintenance: Development on the basis of experience. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    experienced in nuclear power plant operation and maintenance. Worldwide, the average energy availability factor has increased from approximately 70 percent in 1989 to 79 percent' in 1998, with some utilities achieving significantly higher values. This is being achieved through integrated programmes, including personnel training and quality assurance, from improvements implemented in plant systems and components, and from improvements in outage duration for maintenance, refuelling, and other scheduled shutdowns, as well as forced outages. International co-operation is a key role in this success. The various programmes of the World Association of Nuclear Operators (WANO) to exchange information and encourage communication of experience, and the activities of the IAEA including projects in nuclear power plant performance assessment and feedback, effective quality management, and information exchange meetings on technology advances, are important examples of international co-operation to improve the performance of nuclear power plants. This IAEA Technical Committee meeting (TCM) was convened to provide a forum for information exchange on technologies for improving plant operation and maintenance which can contribute to enhanced economic competitiveness of LWRs, and on on-going or planned technology development expected to achieve further improvements. Information exchange of recent positive experience on development and/or implementation of technologies that have resulted in reduced operation and maintenance costs of LWRs, and information on on-going or planned activities, was strongly encouraged.

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

    Science.gov (United States)

    2010-11-30

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

  8. 77 FR 64970 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-10-24

    ... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... observe the business of the Biomass Research and Development Technical Advisory Committee. To attend the... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and...

  9. IAEA technical committee meeting on pellet injection

    International Nuclear Information System (INIS)

    1993-01-01

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

  10. 75 FR 56525 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-09-16

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

  11. 76 FR 38608 - Sensors and Instrumentation Technical Advisory Committee;

    Science.gov (United States)

    2011-07-01

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

  12. 77 FR 50488 - Hydrogen and Fuel Cell Technical Advisory Committee

    Science.gov (United States)

    2012-08-21

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee AGENCY: Department of...). SUMMARY: This notice announces an open meeting (Webinar) of the Hydrogen and Fuel Cell Technical Advisory... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

  13. 77 FR 6791 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-02-09

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy... announces an open meeting of the Biomass Research and Development Technical Advisory Committee. The Federal... leading to the production of biobased fuels and biobased products. Tentative Agenda Update on USDA Biomass...

  14. 77 FR 26276 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-05-03

    ... business of the Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  15. 78 FR 46331 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-07-31

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy.... Appointments to the Biomass Research and Development Technical Advisory Committee will be made by the Secretary... Energy is soliciting nominations for candidates to fill vacancies on the Biomass Research and Development...

  16. 78 FR 44105 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-07-23

    ... Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral statements... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  17. 78 FR 29125 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-05-17

    ... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... public are welcome to observe the business of the Biomass Research and Development Technical Advisory... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and...

  18. 76 FR 63614 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-10-13

    ... Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  19. Introductory statement at the Technical Assistance and Co-operation Committee of the Board of Governors. Vienna, 17 November 2003 [As delivered

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2003-01-01

    The IAEA's technical co-operation (TC) programme is focused on putting advanced science to work to meet the economic and social needs of developing countries. The TC planning process is briefly discussed, including recent evaluation results; highlighting of a number of key activities; and reviewing the current status of TC implementation and funding. The areas of activity include: The use of radiotherapy in cancer treatment; isotope hydrology; monitoring coastal and marine environment; plant breeding applications. Program implementation as well as program funding is discussed. The Agency is also working to reinforce technical co-operation among developing countries (TCDC), that is, the pooling of resources and expertise in areas of mutual benefit. It is stated that the TC programme has become a powerful tool for transferring nuclear science and technology to developing countries. But only if we work together in partnership can we ensure the success of the programme. I look forward to the continuation and further development of that partnership

  20. 76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

    Science.gov (United States)

    2011-05-20

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

  1. 75 FR 30804 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-06-02

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

  2. 75 FR 11526 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-03-11

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

  3. Summary of IAEA technical committee meeting on impurity control

    International Nuclear Information System (INIS)

    Itoh, Kimitaka.

    1989-03-01

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

  4. 78 FR 8500 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-02-06

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... fuels and biobased products. Tentative Agenda: Agenda will include the following: Update on USDA Biomass...

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

    Energy Technology Data Exchange (ETDEWEB)

    Loew, Gregory

    2003-02-21

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

  6. 78 FR 60866 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2013-10-02

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Office of...: This notice announces an open meeting of the Hydrogen and Fuel Cell Technical Advisory Committee (HTAC... Committee: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under section 807...

  7. General report of Technical Committee IV

    International Nuclear Information System (INIS)

    Feinendegen, L.E.

    1979-01-01

    During the report period, work in section IV of the Committee was continued on the molecular, cellular and organic levels with the aim to elucidate the origin, course and treatment possibility of the syndrome that may occur in the mammalian organism upon acute and chronic ionizing irradiation as a function of the radiation dose received. The investigations dealt a.o. with the effect of O 2 in protein radiolysis, recovery processes of the haematopoietic stem cells, delayed effects in the gastrointestical tract subsequent to local irradiation, and combination damage in the lungs and liver of rats upon combined cytostatic and radiation therapy. (orig./HP) [de

  8. INFCE technical co-ordinating committee documents

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-07-01

    A collection of the documents covering the period December 1977 through February 1980 submitted to or generated by the Technical Co-ordinating Comittee is presented. The documents cover primarily the organizational aspects of INFCE, but conclusions from the various Working Groups are summarized.

  9. INFCE technical co-ordinating committee documents

    International Nuclear Information System (INIS)

    A collection of the documents covering the period December 1977 through February 1980 submitted to or generated by the Technical Co-ordinating Comittee is presented. The documents cover primarily the organizational aspects of INFCE, but conclusions from the various Working Trays are summarized

  10. Report From the International Linear Collider Technical Review Committee

    International Nuclear Information System (INIS)

    Loew, Gregory A.

    2003-01-01

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

  11. 76 FR 9339 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-02-17

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and... Biomass Research and Development Technical Advisory Committee under Section 9008(d) of the Food.... Tentative Agenda: Agenda will include the following: Update on USDA Biomass R&D Activities. Update on DOE...

  12. 76 FR 22091 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-04-20

    ... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION: Notice of Open Meeting. SUMMARY: This notice announces an open meeting of the Biomass Research and...

  13. Report of Radioisotope Inspection Technical Committee

    International Nuclear Information System (INIS)

    Otani, H.

    1980-01-01

    For the purpose of unifying the method of performance test for the routine management of the performance of RI equipments, the check-up of performance at the time of purchasing the equipments or research works, the Committee has continued the investigation on the method of performance test on RI equipments. Now, the definite plans have been decided regarding the method of performance test on radioisotope monitoring instruments and the measuring instruments for RI samples, therefore they are reported hereinafter. As for the radioisotope monitoring instruments, Curie meter, area monitor, water monitor, gas monitor and hand, foot and cloth monitor were taken up, and the items of inspection, the purposes, the testing methods, the expression of measured results and their evaluation were discussed. The accuracy of measurement of absolute radio-activity is important in Curie meter, the stability of continuous monitoring is important in general monitors, and the limit of measurement is important in the hand, foot and cloth monitor. As for the measuring instruments for radioactive materials, the efficiency of counting, linearity and stability were taken up as the items of performance test, and other matters to which attention should be paid were added. These were described, dividing into well type scintillation counter and liquid scintillation counter. (Kako, I.)

  14. 75 FR 39919 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-07-13

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

  15. 78 FR 24160 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-04-24

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

  16. 75 FR 64258 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-10-19

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

  17. 78 FR 63162 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-10-23

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

  18. 78 FR 42753 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-07-17

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

  19. 76 FR 64895 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-10-19

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

  20. 76 FR 39845 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-07-07

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

  1. 78 FR 1198 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-08

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

  2. 77 FR 24178 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-04-23

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

  3. 77 FR 37652 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-06-22

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

  4. 77 FR 1666 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2012-01-11

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

  5. 77 FR 18243 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC); Notice of Open Meeting

    Science.gov (United States)

    2012-03-27

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

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

    International Nuclear Information System (INIS)

    1997-09-01

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

  7. 76 FR 46781 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-08-03

    ..., 2011: 7:30 a.m.-2 p.m.; August 24, 2011: 7:30 a.m.-12:30 p.m. ADDRESSES: I Hotel, 1900 S. First Street... welcome to observe the business of the Biomass Research and Development Technical Advisory Committee. To... ext. 220; E- mail: hq.com ">[email protected] hq.com at least 7 business days prior to the meeting. Members...

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

    International Nuclear Information System (INIS)

    2001-05-01

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

  9. Energy Materials Coordinating Committee, fiscal year 1997. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1997 and describes the materials research programs of various offices and divisions within the Department.

  10. 75 FR 62096 - Agricultural Technical Advisory Committees for Trade in Tobacco, Cotton, Peanuts and Planting...

    Science.gov (United States)

    2010-10-07

    ... many of the issues that the GFO committee addresses, such as genetically modified organisms, new... modifying the existing structure of both the Agricultural Technical Advisory Committees (ATAC) for Trade in...

  11. 75 FR 62509 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

    Science.gov (United States)

    2010-10-12

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

  12. 77 FR 2271 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

    Science.gov (United States)

    2012-01-17

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

  13. 78 FR 5774 - Technical Advisory Committees; Notice of Recruitment of Private-Sector Members

    Science.gov (United States)

    2013-01-28

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Technical Advisory Committees; Notice of Recruitment of Private- Sector Members SUMMARY: Seven Technical Advisory Committees (TACs) advise the Department of Commerce on the technical parameters for export controls applicable to dual-use commodities and...

  14. 78 FR 63279 - Third Meeting: RTCA Tactical Operations Committee (TOC)

    Science.gov (United States)

    2013-10-23

    ... Operations Committee (TOC) AGENCY: Federal Aviation Administration (FAA), U.S. Department of Transportation... hereby given for a meeting of the Tactical Operations Committee (TOC). The agenda will include the following: November 19, 2013 Opening of Meeting/Introduction of TOC Members Official Statement of Designated...

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

    Science.gov (United States)

    2011-04-14

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

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

    Science.gov (United States)

    2012-10-11

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

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

    Science.gov (United States)

    2012-06-22

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

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

    Science.gov (United States)

    2010-01-11

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

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

    Science.gov (United States)

    2012-01-17

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

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

    Science.gov (United States)

    2013-01-08

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

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

    Science.gov (United States)

    2011-01-04

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

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

    Science.gov (United States)

    2010-07-13

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

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

    Science.gov (United States)

    2013-04-02

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

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

    Science.gov (United States)

    2011-10-13

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

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

    Science.gov (United States)

    2013-10-01

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

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

    Science.gov (United States)

    2013-07-03

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

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

    Science.gov (United States)

    2012-04-18

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

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

    Science.gov (United States)

    2010-03-25

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

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

    Science.gov (United States)

    2010-10-12

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

  10. The French Space Operation Act: Technical Regulations

    Science.gov (United States)

    Trinchero, J. P.; Lazare, B.

    2010-09-01

    The French Space Operation Act(FSOA) stipulates that a prime objective of the National technical regulations is to protect people, property, public health and the environment. Compliance with these technical regulations is mandatory as of 10 December 2010 for space operations by French space operators and for space operations from French territory. The space safety requirements and regulations governing procedures are based on national and international best practices and experience. A critical design review of the space system and procedures shall be carried out by the applicant, in order to verify compliance with the Technical Regulations. An independent technical assessment of the operation is delegated to CNES. The principles applied when drafting technical regulations are as follows: requirements must as far as possible establish the rules according to the objective to be obtained, rather than how it is to be achieved; requirements must give preference to international standards recognised as being the state of the art; requirements must take previous experience into account. Technical regulations are divided into three sections covering common requirements for the launch, control and return of a space object. A dedicated section will cover specific rules to be applied at the Guiana Space Centre. The main topics addressed by the technical regulations are: operator safety management system; study of risks to people, property, public health and the Earth’s environment; impact study on the outer space environment: space debris generated by the operation; planetary protection.

  11. 76 FR 4645 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2011-01-26

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department...: This notice announces a meeting of the Hydrogen and Fuel Cell Technical Advisory Committee (HTAC). HTAC... Agenda: (Subject to change; updates will be posted on http://hydrogen.energy.gov and copies of the final...

  12. 76 FR 60478 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2011-09-29

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department...: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under section 807 of... website at: http://hydrogen.energy.gov and copies of the final agenda will available the date of the...

  13. 78 FR 6086 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2013-01-29

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Office of...). SUMMARY: This notice announces an open meeting (Webinar) of the Hydrogen and Fuel Cell Technical Advisory... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

  14. 77 FR 2714 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2012-01-19

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department.... SUMMARY: This notice announces an open meeting of the Hydrogen and Fuel Cell Technical Advisory Committee... posted on http://hydrogen.energy.gov ). Public Comment (10 minutes) Discussion of HTAC's draft annual...

  15. 75 FR 59705 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2010-09-28

    ... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department...: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under section 807 of... Agenda Topics: (Subject to change; updates will be posted on the web at http://hydrogen.energy.gov and...

  16. 77 FR 27832 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-05-11

    ... organizations --Relations with non-governmental organizations --World Maritime Day --International Maritime... DEPARTMENT OF STATE [Public Notice: 7879] Shipping Coordinating Committee; Notice of Committee...-second Session of the International Maritime Organization (IMO) Technical Co-operation Committee (TCC 62...

  17. Establishment of strengthening technical cooperation system through the IAEA advisory committee

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Si Hwan; Lee, H. Y.; Kim, Y. T. and others

    2001-03-01

    The International Atomic Energy Agency(IAEA) operates seventeen(17) Standing Advisory Groups(SAG) and nine(9) International Working Groups(IWG). Korean experts are currently participating in most of these advisory groups, but there is something yet to improve especially in faithful reflection of Korean nuclear policy as well as a systematic and effective utilization technical information received in the committee meetings. Therefore, it is necessary firstly to analyze results and systematic follow-up of technology developments for each IAEA committee group to solidate activities of Korean members. Based on these analyses, we can hence support administratively Korean members to do faithful reflection of Korean nuclear policy. In addition, a scheme for systematic management of the information should be drawn up for use of these information effectively for nuclear power projects, R and D, safety regulation, and establishment of nuclear policy in Korea.

  18. Establishment of strengthening technical cooperation system through the IAEA advisory committee

    International Nuclear Information System (INIS)

    Kim, Si Hwan; Lee, H. Y.; Kim, Y. T. and others

    2001-03-01

    The International Atomic Energy Agency(IAEA) operates seventeen(17) Standing Advisory Groups(SAG) and nine(9) International Working Groups(IWG). Korean experts are currently participating in most of these advisory groups, but there is something yet to improve especially in faithful reflection of Korean nuclear policy as well as a systematic and effective utilization technical information received in the committee meetings. Therefore, it is necessary firstly to analyze results and systematic follow-up of technology developments for each IAEA committee group to solidate activities of Korean members. Based on these analyses, we can hence support administratively Korean members to do faithful reflection of Korean nuclear policy. In addition, a scheme for systematic management of the information should be drawn up for use of these information effectively for nuclear power projects, R and D, safety regulation, and establishment of nuclear policy in Korea

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-12-01

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

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

    International Nuclear Information System (INIS)

    2001-12-01

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

  1. 78 FR 16757 - First Meeting: RTCA Tactical Operations Committee (TOC)

    Science.gov (United States)

    2013-03-18

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration First Meeting: RTCA Tactical Operations Committee (TOC) AGENCY: Federal Aviation Administration (FAA), U.S. Department of Transportation... FAA Task Groups Discussion Anticipated Issues for TOC consideration and action at the next meeting...

  2. 78 FR 40264 - First Meeting: RTCA Tactical Operations Committee (TOC)

    Science.gov (United States)

    2013-07-03

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration First Meeting: RTCA Tactical Operations Committee (TOC) AGENCY: Federal Aviation Administration (FAA), U.S. Department of Transportation..., Leadership Anticipated Issues for TOC consideration and action at the next meeting. Any Other Business...

  3. International Linear Collider Technical Review Committee Report, 1995

    International Nuclear Information System (INIS)

    1995-12-01

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

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

    International Nuclear Information System (INIS)

    1996-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

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

  6. Brief Introduction of Chinese National Technical Committee for Standardization on Radio Interference

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    @@ Chinese Nationa Technical Committee for Standardization on Radio Interference(SAC/TC79),ESTABLISHED IN 1986,is the national technical organization relating to different departments for standardization,with responsibility for technical research of electromagnetic compatibility as well as the management of each subcommittee.

  7. Technical support for nuclear power operations

    International Nuclear Information System (INIS)

    1999-04-01

    This report prepared by the group of senior experts from nuclear operating organizations in Member states, addresses the problem of improving the operating performance of nuclear power plants. Safe and reliable operation is essential for strengthening the viability of nuclear power in the increasingly competitive market of electric power. Basic principles and requirements concerning technical procedures and developed practices are discussed. Report reflects the best current international practices and presents those management initiatives that go beyond the mandated regulatory compliance and could lead to enhancement od operational safety and improved plant performance. By correlating experiences and presenting collective effective practices it is meant to assist nuclear power plant managers in achieving improvement in operation through the contribution of effective technical support

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

    International Nuclear Information System (INIS)

    1997-05-01

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

  9. 76 FR 33701 - Agricultural Technical Advisory Committees for Trade; Renewal

    Science.gov (United States)

    2011-06-09

    ... many of the issues that the GFO committee addresses, such as genetically modified organisms, new... Vegetables; Processed Foods, and; Sweeteners and Sweetener Products. Pursuant to the Federal Advisory...

  10. Proceedings of the technical committee on high conversion and high burnup reactors

    International Nuclear Information System (INIS)

    Shiroya, Seiji; Kanda, Keiji; Sekiya, Tamotsu

    1990-02-01

    The present issue is the proceedings of 'the Technical Committee on High Conversion and High Burnup Reactors' held at Kyoto University Research Reactor Institute (KURRI) on December 12 and 22, 1988. In this committee, members so much concerned with this theme were asked to report their recent accomplishment and activities. By such a program, the committee was intended to make a survey of future direction of research in this type of reactor. (J.P.N.)

  11. 77 FR 66178 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2012-11-02

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

  12. 78 FR 63161 - Sensors and Instrumentation Technical Advisory Committee; Notice of Partially Closed Meeting...

    Science.gov (United States)

    2013-10-23

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

  13. 75 FR 23223 - Meetings of the Agricultural Policy Advisory Committee for Trade and the Agricultural Technical...

    Science.gov (United States)

    2010-05-03

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

  14. 75 FR 68008 - Business and Operations Advisory Committee

    Science.gov (United States)

    2010-11-04

    ... NATIONAL SCIENCE FOUNDATION Business and Operations Advisory Committee ACTION: Change in Notice of Meeting. SUMMARY: The National Science Foundation published a Notice of Meeting in the Federal Register on... business operations. Agenda November 16, 2010 Welcome/Introductions; BFA Update; The Changing Workplace...

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

    International Nuclear Information System (INIS)

    2002-07-01

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

  16. Cooperation of technical support organizations of state nuclear regulatory committee of Ukraine in sip safety regulation

    International Nuclear Information System (INIS)

    Bikov, V.O.; Kyilochits'ka, T.P.; Bogorins'kij, P.; Vasil'chenko, V.M.; Kondrat'jev, S.M.; Smishlyajeva, S.P.; Troter, D.

    2002-01-01

    The main task of the technical support in the Shelter Implementation Plan (SIP) licensing process consists in Technical Evaluation of SIP projects and documents submitted by the Licensee to State Nuclear Regulatory Committee to substantiate the safety of Shelter-related work. The goal of this task is to evaluate the submitted materials whether they meet the requirements of nuclear and radiation safety

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

    International Nuclear Information System (INIS)

    1997-10-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  19. 76 FR 64892 - Agricultural Policy Advisory Committee and the Agricultural Technical Advisory Committees for...

    Science.gov (United States)

    2011-10-19

    ... balance on each committee will also be sought. Nominations: Nominating a person to serve on any of the... indicating the specific committee for which the individual is being nominated, why the nominee wants to be a... and will not adversely affect his or her ability to serve as an advisor on the U.S. agriculture...

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

    International Nuclear Information System (INIS)

    1996-01-01

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

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

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

  4. 75 FR 16197 - NASA Advisory Council; Space Operations Committee; Meeting

    Science.gov (United States)

    2010-03-31

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-036)] NASA Advisory Council; Space..., the National Aeronautics and Space Administration announces a meeting of the NASA Advisory Council Space Operations Committee. DATES: Tuesday, April 13, 2010, 3-5 p.m. CDT. ADDRESSES: NASA Johnson Space...

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

    International Nuclear Information System (INIS)

    1997-11-01

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

  6. Report of the Technical Committee for Hospitality, Tourism, Recreation.

    Science.gov (United States)

    Oregon State Dept. of Education, Salem. Div. of Vocational Education.

    This color-coded committee report identifies the skills and knowledge required by employees in the hospitality/tourism/recreation occupational area. The reports of four subcommittees focused on food/beverage, hotel/motel, recreation/leisure, and travel/tourism skills are also included. Introductory materials include a general statement of the…

  7. 77 FR 47047 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-08-07

    ... Committee Act (Public Law No. 92-463, 86 Stat. 770) requires that agencies publish these notices in the.... ADDRESSES: Renaissance DuPont Hotel, 1143 New Hampshire Avenue, NW., Washington, DC 20037. FOR FURTHER...: In keeping with procedures, members of the public are welcome to observe the business of the Biomass...

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

    International Nuclear Information System (INIS)

    1997-12-01

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

  9. IAEA Technical Co-operation activities: Africa

    International Nuclear Information System (INIS)

    Bakr, A.A.

    1976-01-01

    In 1975 Tanzania became the newest African Member State of the International Atomic Energy Agency, bringing the total African membership of the Agency up to 25 countries. The other African Member States are: Algeria; United Republic of Cameroon; Egypt; Ethiopia; Gabon; Ghana; Ivory Coast; Kenya; Liberia; Libyan Arab Republic; Madagascar; Mali; Mauritius; Morocco; Niger; Nigeria; Senegal; Sierra Leone; South Africa; Sudan; Tunisia; Uganda; Zaire; Zambia. Membership of the Agency entitles these countries to receive assistance both from the Regular Programme of the Agency and from UNDP resources, while non-Member States in the region only receive Agency assistance financed from the latter source. Any attempt to look at the technical co-operation programme in Africa must start by stressing the wide differences between African countries in their level of scientific and technical development ranging from countries with advanced atomic energy programmes to countries just crossing the threshold towards the peaceful use of nuclear energy. Perhaps the most striking and marked difference is in the quality and number of nuclear energy scientists and technologists available. In view of this, the technical assistance programme in the African context has been a selective one, guided by considerations of pragmatism and responsiveness to particular requirements of the different individual countries and not by any doctrinaire or ready-made strategy for assistance. (author)

  10. 11. annual report of the technical advisory committee on the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    1990-10-01

    The Eleventh Annual Report of the Technical Advisory Committee (TAC) assesses the scientific and technical progress made within the Canadian Nuclear Fuel Waste Management Program (NFWMP) during the period July 1989 to June 1990. The Committee notes that the general concept of a multibarrier system involving geologic media and engineered systems is based on known technologies and current scientific knowledge, and has gained strong international scientific and engineering support as currently the most feasible and practical. TAC continues to endorse the full investigation of the concept of nuclear waste disposal deep in plutonic formations, such as those in the Canadian Shield

  11. Minutes of 'Technical Committee for Geological Isolation Research and Development (1st time)'

    International Nuclear Information System (INIS)

    Sasaki, Yasuo; Torata, Shinichiro

    2007-03-01

    In order to plan and conduct a program of research and development (R and D) for geological disposal of high-level radioactive waste in JAEA-Tokai, JAEA decided to receive technical comments and advices from the Technical Committee for geological isolation R and D. This committee, which is constituted of specialists who do not belong to JAEA, has evaluated the program, taking into account of the status of geological disposal technology in Japan as well as foreign countries. This report compiles the minutes of the first meeting held in July 2006. (author)

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

    International Nuclear Information System (INIS)

    1997-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1955-09-16

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

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

    International Nuclear Information System (INIS)

    TCV team

    1995-11-01

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

  17. The Involvement of Career and Technical Education Advisory Committees in Modularizing Curriculum

    Science.gov (United States)

    Malosh, Ann M.

    2012-01-01

    The emergence of modularized curriculum in community college career and technical education (CTE) programs has received substantial attention over the last decade, with researchers suggesting that this type of curriculum redesign may assist with student retention and success. The purpose of this study was to describe advisory committee member…

  18. 75 FR 75186 - Interview Room Video System Standard Special Technical Committee Request for Proposals for...

    Science.gov (United States)

    2010-12-02

    ... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1534] Interview Room Video System Standard Special Technical Committee Request for Proposals for Certification and Testing Expertise... Interview Room Video System Standard and corresponding certification program requirements. This work is...

  19. 76 FR 323 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2011-01-04

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

  20. 77 FR 65542 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2012-10-29

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Hydrogen and Fuel Cell... Energy. ACTION: Notice of Open Meeting. SUMMARY: The Hydrogen and Fuel Cell Technical Advisory Committee... Agenda: (updates will be posted on the web at: http://hydrogen.energy.gov ). Public Comment DOE Program...

  1. 75 FR 2860 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Hydrogen and Fuel Cell... Energy. ACTION: Notice of Open Meeting. SUMMARY: The Hydrogen and Fuel Cell Technical Advisory Committee... change; updates will be posted on http://hydrogen.energy.gov and copies of the final agenda will...

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

    International Nuclear Information System (INIS)

    1999-12-01

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

  3. 78 FR 65265 - Materials Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2013-10-31

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

  4. Technical committee on transport package test standards, Tokyo, Japan, 28 September - 2 October 1981

    International Nuclear Information System (INIS)

    Ek, P.

    The Technical Committee looked into the following tasks: a) the additional 200 m water immersion test for packages designed for irradiated fuel when the activity exceeds 10 6 Ci; b) the proposed addition of a crush test for light weight Type B and fissile materials packages; c) the proposed new text for thermal test

  5. Report of the Subcommittee for Travel/Tourism of the Hospitality/Tourism/Recreation Technical Committee.

    Science.gov (United States)

    Oregon State Dept. of Education, Salem. Div. of Vocational Education.

    Written by a technical committee's industry representatives, state officials, and educators in Oregon, this document lists the skills and knowledge required by employees in travel and tourism occupations. The following occupations are considered: rental representative; service agent; travel agent; bus/tour/driver/guide/sightseeing leader; manager…

  6. DOE Advanced Scientific Computing Advisory Committee (ASCAC) Subcommittee Report on Scientific and Technical Information

    Energy Technology Data Exchange (ETDEWEB)

    Hey, Tony [eScience Institute, University of Washington; Agarwal, Deborah [Lawrence Berkeley National Laboratory; Borgman, Christine [University of California, Los Angeles; Cartaro, Concetta [SLAC National Accelerator Laboratory; Crivelli, Silvia [Lawrence Berkeley National Laboratory; Van Dam, Kerstin Kleese [Pacific Northwest National Laboratory; Luce, Richard [University of Oklahoma; Arjun, Shankar [CADES, Oak Ridge National Laboratory; Trefethen, Anne [University of Oxford; Wade, Alex [Microsoft Research, Microsoft Corporation; Williams, Dean [Lawrence Livermore National Laboratory

    2015-09-04

    The Advanced Scientific Computing Advisory Committee (ASCAC) was charged to form a standing subcommittee to review the Department of Energy’s Office of Scientific and Technical Information (OSTI) and to begin by assessing the quality and effectiveness of OSTI’s recent and current products and services and to comment on its mission and future directions in the rapidly changing environment for scientific publication and data. The Committee met with OSTI staff and reviewed available products, services and other materials. This report summaries their initial findings and recommendations.

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

    International Nuclear Information System (INIS)

    1997-08-01

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

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

    International Nuclear Information System (INIS)

    1996-11-01

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

  9. Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

    International Nuclear Information System (INIS)

    Little, C.A.

    1995-01-01

    The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author's responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A

  10. Committee on the safety of nuclear installations - Operating plan (2006 - 2009)

    International Nuclear Information System (INIS)

    2007-01-01

    In 2004, NEA issued its Strategic Plan covering the period 2005-2009, addressing the NEA activities associated with nuclear safety and regulation. Committee on the Safety of Nuclear Installations (CSNI) and Committee on Nuclear Regulatory Activities (CNRA), which have the primary responsibility for activities in this area, have developed and issued a joint strategic plan covering this same time period. As requested in the Joint Strategic Plan, each committee is to prepare an operating plan which describes in more detail the committee's organisation, planned activities, priorities and operating procedures to be used to implement the Joint Strategic Plan. In effect, the Joint Strategic Plan defines what type of work CSNI should do, whereas the Operating Plan describes the overall work scope and how to accomplish it to meet the joint CSNI/CNRA Strategic Plan objectives and mission. The present Operating Plan follows and takes into account the outcome of a CSNI assessment group, which has evaluated the CSNI activities. The assessment group expressed appreciation for the CSNI role and activity, while making recommendations with regards to scope of work and way to operate in order to further improve efficiency. The main objectives of CSNI are to: - Keep all member countries involved in and abreast of developments in safety technology. - Review operating experience with the objective to identify safety issues that need to be addressed by new research. - Review the state-of-knowledge on selected topics of nuclear safety technology and safety assessment. - Promote training and research projects that serve to maintain competence in nuclear safety matters. - Promote research as needed to reach consensus on nuclear safety issues of common interest. - Consider the safety implications of scientific and technical developments. To accomplish these objectives, CSNI is organised into six permanent working groups (as described in Section II), each covering a different set of

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

    International Nuclear Information System (INIS)

    2001-05-01

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

  12. IAEA technical committee on advances in inertial confinement systems

    International Nuclear Information System (INIS)

    Peacock, N.J.

    1980-01-01

    In the United Kingdom there is no national inertial confinement programme directed towards civil reactor use. The programme for Controlled Fusion Research, which forms part of the UKAEA Research Group activities, is located at the Culham Laboratory. At this centre, fusion research is devoted entirely to magnetic confinement systems. A fraction of the total effort involves the development and use of powerful lasers for diagnostic purposes, for toroidal plasma refuelling schemes, for basic studies of laser-plasma interactions, highly-ionised atoms and XUV light gain experiments, and for certain commercial applications. Within the universities there is a widespread interest in laser systems and laser-plasma interactions. The substantial research facilities in the Laser Division of the Rutherford Laboratory (SRC) provides a focus for these activities. These lasers are operated as a university users' facility. A two beam, neodymium in phosphate, glass laser (operating at 0.6 TW/beam, but presently being upgraded) is the Rutherford Laboratory's major laser system for implosion and compression studies. Sophisticated radiation diagnostics are a feature of this work. In a single-beam mode, the glass laser has been used for a great deal of laser-plasma interaction physics e.g. non-linear absorption, inhibited heat conduction and harmonic self-generation. Atomic structure of highly-ionised atoms, plasma line broadening and XUV light gain experiments are also active research topics. Concurrent with upgrading the glass laser facility to 6 x 1 TW beams, experiments on harmonic conversion of the output to 2ω 0 , 4ω 0 are being pursued. Electron beam-pumped, rare-gas halide, eximer systems operating in the blue region of the spectrum are also being investigated. The universities provide a considerable back-up for the work at the Rutherford Laser Division. (J.P.N.)

  13. Technical and operational assessment of molecular nanotechnology for space operations

    Science.gov (United States)

    McKendree, Thomas Lawrence

    2001-07-01

    This study assesses the performance of conventional technology and three levels of molecular nanotechnology (MNT) for space operations. The measures of effectiveness are technical performance parameters for five space transportation architectures, and the total logistics cost for an evaluation scenario with mining, market and factory locations on the Moon, Mars and asteroids. On these measures of effectiveness, improvements of 2--4 orders of magnitude are seen in chemical rockets, solar electric ion engines, solar sail accelerations (but not transit times), and in structural masses for planetary skyhooks and towers. Improvements in tether performance and logistics costs are nearer to 1 order of magnitude. Appendices suggest additional improvements may be possible in space mining, closed-environment life support, flexible operations, and with other space transportation architectures. In order to assess logistics cost, this research extends the facility location problem of location theory to orbital space. This extension supports optimal siting of a single facility serving circular, coplanar orbits, locations in elliptic planetary and moon orbits, and heuristic siting of multiple facilities. It focuses on conventional rocket transportation, and on high performance rockets supplying at least 1 m/s2 acceleration and 500,000 m/s exhaust velocity. Mathematica implementations are provided in appendices. Simple MNT allows diamond and buckytube construction. The main benefits are in chemical rocket performance, solar panel specific power, solar electric ion engine performance, and skyhook and tower structural masses. Complex MNT allows very small machinery, permitting large increases in solar panel specific power, which enables solar electric ion engines that are high performance rockets, and thus reduces total logistics costs an order of magnitude. Most Advance MNT allows molecular manufacturing, which enables self-repair, provides at least marginal improvements in nearly

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

    International Nuclear Information System (INIS)

    2002-06-01

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

  15. Energy Materials Coordinating Committee (EMaCC): Annual technical report, Fiscal year 1987

    International Nuclear Information System (INIS)

    1988-09-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1987 and describes the materials research programs of various offices and divisions within the Department

  16. Estimation of regulated term of technical systems further operation

    International Nuclear Information System (INIS)

    Strel'nikov, V.P.

    2008-01-01

    The technique of estimating the regulated term of technical systems further operation on the basis of data on failures during operation and use of probabilistic-physical model of failures (DN-distribution) is proposed

  17. Energy Materials Coordinating Committee (EMaCC). Annual technical report, Fiscal Year 2001

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2002-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations.

  18. H2 at Scale: Benefitting our Future Energy System - Update for the Hydrogen Technical Advisory Committee

    Energy Technology Data Exchange (ETDEWEB)

    Ruth, Mark

    2016-12-06

    Hydrogen is a flexible, clean energy carrying intermediate that enables aggressive market penetration of renewables while deeply decarbonizing our energy system. H2 at Scale is a concept that supports the electricity grid by utilizing energy without other demands at any given time and also supports transportation and industry by providing low-priced hydrogen to them. This presentation is an update to the Hydrogen Technical Advisory Committee (HTAC).

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

    International Nuclear Information System (INIS)

    1996-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

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

  1. Technical committee on transport package test standards (for radioactive materials transport). Vienna, 6-10 August 1979

    International Nuclear Information System (INIS)

    White, M.C.

    1979-11-01

    The report of a meeting of the technical committee on transport package test standards is presented. The committee assigned high priority to work on Low Level Solid material and Low Specific Activity material, on the justification for and requirements of a Crush Test and on leakage from packages

  2. Document collection of the 28th technical special committee on Fugen decommissioning

    International Nuclear Information System (INIS)

    Kutsuna, Hideki; Iwai, Hiroki; Mizui, Hiroyuki; Kadowaki, Haruhiko; Nakamura, Yasuyuki

    2014-02-01

    Fugen Decommissioning Engineering Center, in planning and carrying out our decommissioning technical development, has been establishing “Technical special committee on Fugen decommissioning” which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials “The Current Situation of Fugen Decommissioning”, “The Current Status of the Cutting Test toward the Practical Use of Laser Cutting Technology and the Future Plan”, “Study on Radioactive Substance Osmosis for Basis Concrete of Equipment”, “Verification Tests of the Room-Temperature Vacuum Drying and the Evaluation Method of Residual Amount of Heavy Water in the Tritium Removal” and “Report on the FUGEN Efforts of R and D for Decommissioning of the Fukushima Daiichi NPS - Applicability Test of Thermal and Mechanical Cutting Technology for the Dismantlement of the Internal Core of Fukushima Daiichi NPS -”, presented in the 28th Technical special committee on Fugen decommissioning which was held on September 24, 2013. (author)

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

    International Nuclear Information System (INIS)

    1998-06-01

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

  4. Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department.

  5. Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

    International Nuclear Information System (INIS)

    1997-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-07-01

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

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

    International Nuclear Information System (INIS)

    1990-01-01

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

  8. 78 FR 32698 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2013-05-31

    ... DEPARTMENT OF STATE [Public Notice 8340] Shipping Coordinating Committee; Notice of Committee... Technical Co-operation Committee --Protection of vital shipping lanes --Periodic review of administrative... of the Organization since the twenty-eighth regular session of the Assembly --External relations...

  9. Development of international standards for surface analysis by ISO technical committee 201 on surface chemical analysis

    International Nuclear Information System (INIS)

    Powell, C.J.

    1999-01-01

    Full text: The International Organization for Standardization (ISO) established Technical Committee 201 on Surface Chemical Analysis in 1991 to develop documentary standards for surface analysis. ISO/TC 201 met first in 1992 and has met annually since. This committee now has eight subcommittees (Terminology, General Procedures, Data Management and Treatment, Depth Profiling, AES, SIMS, XPS, and Glow Discharge Spectroscopy (GDS)) and one working group (Total X-Ray Fluorescence Spectroscopy). Each subcommittee has one or more working groups to develop standards on particular topics. Australia has observer-member status on ISO/TC 201 and on all ISO/TC 201 subcommittees except GDS where it has participator-member status. I will outline the organization of ISO/TC 201 and summarize the standards that have been or are being developed. Copyright (1999) Australian X-ray Analytical Association Inc

  10. 78 FR 20696 - NASA Advisory Council; Human Exploration and Operations Committee; Research Subcommittee; Meeting

    Science.gov (United States)

    2013-04-05

    ... topics: --Overview of Research in Space Life and Physical Sciences --Space Station and Future Exploration... Exploration and Operations Committee; Research Subcommittee; Meeting AGENCY: National Aeronautics and Space... of the Research Subcommittee of the Human Exploration and Operations Committee (HEOC) of the NASA...

  11. 75 FR 21678 - Business and Operations Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2010-04-26

    ... Management/Leadership Development. May 19, 2010 NSF Strategic Plan Update--2010-2015; Future NSF-2013 Lease... NATIONAL SCIENCE FOUNDATION Business and Operations Advisory Committee; Notice of Meeting In... announces the following meeting: Name: Business and Operations Advisory Committee (9556). Date/Time: May 18...

  12. 76 FR 19355 - Notice of Staff Attendance at Southwest Power Pool Markets Operations Policy Committee Meeting

    Science.gov (United States)

    2011-04-07

    ...) Markets Operations Policy Committee (MOPC), as noted below. Their attendance is part of the Commission's... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Notice of Staff Attendance at Southwest Power Pool Markets Operations Policy Committee Meeting The Federal Energy Regulatory Commission hereby...

  13. 75 FR 6656 - SFIREG Pesticide Operations and Management Working Committee Meeting

    Science.gov (United States)

    2010-02-10

    ... Evaluation Group (SFIREG), Pesticide Operations and Management (POM) Working Committee will hold a 2-day... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-OPP-2010-0001; FRL-8811-3] SFIREG Pesticide Operations and Management Working Committee Meeting AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY...

  14. 42nd Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-13-01)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 42nd plenary on 8-12 April 2013 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics dea...... were inter alia assessments of Mediterranean Sea stocks, future EU data collection, and technical measures.......The Scientific, Technical and Economic Committee for Fisheries hold its 42nd plenary on 8-12 April 2013 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics dealt...

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

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

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

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2005-06-01

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

  18. Energy Materials Coordinating Committee (EMaCC) Fiscal Year 1999 annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-10-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1999 and describes the materials research programs of various offices and divisions within the Department.

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

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2004-12-01

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

  20. Thirteenth annual report of the Technical Advisory Committee on the Nuclear Fuel Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-15

    This report details activities since the last reporting period by the Technical Advisory Committee (TAC). The emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of the primary reference document as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO).

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

    International Nuclear Information System (INIS)

    1997-03-01

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

  2. Technical Co-operation between developing countries

    International Nuclear Information System (INIS)

    2001-01-01

    In the plan of activities of the project Int/0/060 Technical Cooperation Between Developing Countries a Workshop on Public Awareness Promotional Literature was included with the purpose of preparing public and professional awareness literature and to develop a strategy which would enable Tissue Banks to present their mission to their public,professional health workers and clinical users.To identify the information to be provided to potential donors about the value of the donation.To prepare instructions to be given to potential users about the various types of grafts available.To develop a strategy wi ch would enable Tissue Banks to present themselves to their public and tissue users

  3. Quantum operations: technical or fundamental challenge?

    International Nuclear Information System (INIS)

    Mielnik, Bogdan

    2013-01-01

    A class of unitary operations generated by idealized, semiclassical fields is studied. The operations implemented by sharp potential kicks are revisited and the possibility of performing them by softly varying external fields is examined. The possibility of using the ion traps as ‘operation factories’ transforming quantum states is discussed. The non-perturbative algorithms indicate that the results of abstract δ-pulses of oscillator potentials can become real. Some of them, if empirically achieved, could be essential to examine certain atypical quantum ideas. In particular, simple dynamical manipulations might contribute to the Aharonov–Bohm criticism of the time–energy uncertainty principle, while some others may verify the existence of fundamental precision limits of the position measurements or the reality of ‘non-commutative geometries’. (paper)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

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

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

    International Nuclear Information System (INIS)

    2000-02-01

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

  8. 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

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

    International Nuclear Information System (INIS)

    1997-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

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

  11. Technical co-operation for nuclear safety in developing countries

    International Nuclear Information System (INIS)

    Flakus, F.N.; Giuliani, P.

    1984-01-01

    The Agency's programme on technical co-operation for nuclear safety is, largely, responsive in character and the Agency's response is tailored to needs identified by developing countries. However, the Agency's assistance alone is not sufficient: technical co-operation can only be successful and is most effective when there is also a strong input from the counterpart body participating in a particular project. The commitment of national governments is fundamental to success. Technical co-operation is most fruitful if the Agency's assistance capabilities and the recipient country's co-operation capabilities match. Co-operation activities mostly take the form of single projects hosted by individual institutions within a single country; regional and inter-regional projects are also important

  12. Technical and organizational support for the operator

    International Nuclear Information System (INIS)

    Harrison, J.R.; Prescott, W.

    1981-01-01

    The requirement for staff and facilities on- and off-site to provide technical support to the plant personnel in normal and under accident conditions has been highlighted over the past 18 months as part of the post-TMI investigations. In the Central Electricity Generating Board (CEGB) considerable attention has always been paid to these requirements but naturally the experience of TMI has led to a review of the existing arrangements to determine whether any improvements and modifications were advisable. Similarly, the CEGB has always paid particular attention to the development of an appropriate emergency plant covering both the on-site damage control activities and off-site evacuation procedures consistent with the demography of the particular site being considered. An important aspect of gaining confidence in the potential success of the emergency plan is the regular practice and exercising of individual parts of the plan and its totality, and full attention is given also to these aspects. The paper reviews in some detail the ways in which the CEGB has met the requirements for the different aspects enumerated above, and will trace the approaches which have developed in the training and practices in respect of accident procedures. (author)

  13. The JMTR operation and technical development, 3

    International Nuclear Information System (INIS)

    1989-10-01

    The JMTR complex consists of a 50MW high neutron flux reactor (JMTR; Japan Materials Testing Reactor), the irradiation facilities, a hot laboratory and a nuclear critical assembly (JMTRC; Japan Materials Testing Reactor Critical Assembly). Many irradiation examinations have been carried out by the capsules, hydraulic rabbits and loop facilities in the JMTR since 1971 when 50MW high power operation was attained. These irradiation facilities and any post irradiation examination equipments have been fabricated, modified and replaced to meet the needs of the times. And now, one gas loop (OGL-1; Oarai Gas Loop-1), two water loops (OWL-2; Oarai Water Loop-2, OSF-1; Oarai Shround Facility-1), two hydraulic rabbits and any capsules are in the JMTR. This report describes the activities of the JMTR project performed in fiscal year 1986∼1988 as following; 1) the operations and maintenances of the JMTR complex, 2) fabrication of the operation backup systems of the reactor and irradiation facilities, 3) JMTR driver fuel enrichment reduce program, 4) the fabrications, modifications and replacements of the irradiation facilities and reactor core components, 5) any irradiation tests by the capsules, 6) developments of the irradiation techniques and post irradiation examination techniques, 7) the fundamental studies to conduct irradiation techniques, 8) future program in the JMTR. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

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

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

    International Nuclear Information System (INIS)

    2002-03-01

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

  16. The JMTR operation and technical development, 4

    International Nuclear Information System (INIS)

    1990-11-01

    The JMTR complex consists of a 50 MW high neutron flux reactor (JMTR; Japan Materials Testing Reactor), the irradiation facilities, a hot laboratory and nuclear critical assembly (JMTRC; Japan Materials Testing Reactor Critical Assembly). Many irradiation examination have been carried out by the capsules, hydraulic rabbit and loop facilities in the JMTR since 1971 when 50 MW high power operation started. These irradiation facilities have been fabricated, modified and replaced according to the needs of the times. And now, one high temperature gas loop (OGL-1, Oarai Gas Loop-1), two water loop (OWL-2; Oarai Water Loop-2, OSF-1; Oarai Shroud Facility), two hydraulic rabbit facilities and many capsules are in the JMTR. And post irradiation examination equipments have been developed according to the needs. This report describes the activities of JMTR Project performed in fiscal year 1989 as following; 1) The operation and management of the JMTR, Hot Laboratory and the JMTRC, 2) utilization status of the JMTR, 3) conversion to Low Enrichment Uranium Fuel, 4) fabrication, modification and replacement of the irradiation facilities and reactor core components, 5) development of the irradiation techniques and post irradiation examination techniques, 6) the fundamental studies to conduct irradiation techniques, 7) future program of the JMTR. (author)

  17. 76 FR 76712 - Notice of Staff Attendance at Southwest Power Pool Markets and Operations Policy Committee Meeting

    Science.gov (United States)

    2011-12-08

    .... Markets and Operations Policy Committee. Their attendance is part of the Commission's ongoing outreach... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Notice of Staff Attendance at Southwest Power Pool Markets and Operations Policy Committee Meeting The Federal Energy Regulatory Commission...

  18. Committees

    Science.gov (United States)

    2012-11-01

    Quebec IREQ, Varennes Canada Etienne PARKINSON Andritz Hydro Ltd. Switzerland B V S S S PRASAD Indian Institute of Technology Madras India Stefan RIEDELBAUCH Stuttgart University Germany Michel SABOURIN Alstom Hydro Canada Inc Canada Bruno SCHIAVELLO Flowserve Corporation USA Katsumasa SHIMMEI Hitachi Ltd Japan Christoph SINGRTüN VDMA Germany Ale? SKOTAK CKD Blansko Engineering, a s Czech Republic Toshiaki SUZUKI Toshiba Corporation Japan Andy C C TAN Queensland University of Technology Australia Geraldo TIAGO FILHO Universidade Federal de Itajuba Brazi Thi C VU Andritz Hydro Ltd Canada Satoshi WATANABE Kyushu University Japan S H WINOTO National University of Singapore Singapore Woo-Seong WOO STX Institute of Technology Korea International Technical Committee François AVELLAN (principal) EPFL-LMH Switzerland Xingqi LUO (principal) Xi'an University of Technology China Martin BÖHLE Kaiserslautern University Germany Gerard BOIS ENSAM France Young-Seok CHOI KITECH Korea Luca d'AGOSTINO University of Pisa Italy Eduard EGUSQUIZA Polytechnical University Catalonia Spain Arpad FAY University of Miskolcz Hungary Richard FISHER Voith Hydro Inc USA Regiane FORTES-PATELLA Institute Polytechnique de Grenoble France Aleksandar GAJIC University of Belgrade Serbia José GONZÁLEZ Universidad de Oviedo Spain François GUIBAULT Ecole Polytechnique de Montreal Canada Toshiaki IKOHAGI Tohoku University Japan Chisachi KATO University of Tokyo Japan Kwang-Yong KIM Inha University Korea Youn-Jea KIM Sungkyunkwan University Korea Smaine KOUIDRI Université Pierre et Marie Curie (Paris 6) France Shengcai LI Warwick University UK Adrian LUNGU Dunarea de Jos University of Galati Romania Torbjøm K NIELSEN NTNU Norway Michihiro NISHI Tsinghua University China Peter PELZ Darmstadt University Germany Frantisek POCHYLY Brno University Czech Republic Albert RUPRECHT University of Stuttgart Germany Rudolf SCHILLING Technische University München Germany Wei SHYY HKUST Hong Kong,China Romeo SUSAN

  19. The Agency's Technical Co-operation activities in 1984. Report by the Director General

    International Nuclear Information System (INIS)

    1985-08-01

    1984 made it possible to achieve substantial increases in the implementation of the expert and training components. In 1984, almost 2700 individuals were involved in the programme, as experts, lecturers, fellows, scientific visitors and training course participants. This represents an increase of about one third over 1983. Regarding the third aim, the Technical Co-operation Evaluation Unit introduced an interim project implementation reporting system in 1984 which relies on national counterparts to report regularly on the progress of their projects; in this way, the Secretariat is alerted to implementation problems as they arise. Approximately 65% of all on-going projects had been covered by this system by the end of 1984. Work on the technical co-operation computer system continued during the year, information on UNDP-financed projects being added to the system and considerable improvements being made to the programs dealing with expert recruitment. For the purpose of monitoring and analysing data related to new assistance requests, a 'project pipeline system' was designed and made operational for use on microcomputers. The system facilitates the preparation of documentation for the Technical Assistance and Co-operation Committee. A Joint Inspection Unit (JIU) study of Agency technical co-operation, which began in 1983, was completed in 1984. In its report, the JIU concluded that Agency assistance was indeed valuable to Member States and that project implementation proceeded in most instances without delay. The Technical Assistance and Co-operation Committee and the Board assessed the JIU's report, endorsing most of the recommendations put forward. A management review of technical co-operation was completed in 1984 by an independent consultant. As a result, a number of actions are planned that should help the Secretariat to cope more effectively with increasing responsibilities in the coming years

  20. The Agency's technical co-operation activities in 1992

    International Nuclear Information System (INIS)

    1993-08-01

    This report on the International Atomic Energy Agency's Technical Co-operation Activities in 1992 contains an overview of the general issues involved, including both in-house and external developments, resources and delivery, and evaluation of programs; an overview by field of activity and by division within the Agency; an overview by geographic area, distinguishing (i) Africa, (ii) Asia and the Pacific, (iii) Latin America, (iv) and the Middle East and Europe; an overview by component (i.e., experts, equipment, fellowships, training courses, sub-contracts and miscellaneous); and an overview by fund technical assistance and co-operation fund, extrabudgetary resources, United Nations Development Program (UNDP), assistance in kind. It also contains a profile on technical co-operation activities in Latin America. Projects concluded during 1992 are listed together with a description of their achievements. It concludes with implementation summaries. 10 figs, 9 tabs

  1. Impact of three years training on operations capacities of research ethics committees in Nigeria.

    Science.gov (United States)

    Folayan, Morenike Oluwatoyin; Adaranijo, Aisha; Durueke, Florita; Ajuwon, Ademola; Adejumo, Adebayo; Ezechi, Oliver; Oyedeji, Kola; Akanni, Olayide

    2014-04-01

    This paper describes a three-year project designed to build the capacity of members of research ethics committes to perform their roles and responsibilities efficiently and effectively. The project participants were made up of a cross-section of the membership of 13 Research Ethics Committees (RECs) functioning in Nigeria. They received training to develop their capacity to evaluate research protocols, monitor trial implementation, provide constructive input to trial staff, and assess the trial's success in promoting community engagement in the research. Following the training, technical assistance was provided to participants on an ongoing basis and the project's impacts were assessed quantitatively and qualitatively. Results indicate that sustained investment in capacity building efforts (including training, ongoing technical assistance, and the provision of multiple tools) improved the participants' knowledge of both the ethical principles relevant to biomedical research and how effective REC should function. Such investment was also shown to have a positive impact on the knowledge levels of other RECs members (those who did not receive training) and the overall operations of the RECs to which the participants belonged. Building the capacity of REC members to fulfill their roles effectively requires sustained effort and investment and pays off by enabling RECs to fulfill their essential mission of ensuring that trials are conducted safely and ethically. © 2012 John Wiley & Sons Ltd.

  2. Energy materials coordinating committee (EMACC) Fiscal Year 1982. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1983-03-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/ workshops on selected topics involving both DOE and major contractors. In addition, the EMaCC aids in obtaining materials - related inputs for both intra- and interagency compilations. Membership in the EMaCC is open to any Department organizational unit; participants are appointed by Division or Office Directors. The current membership is listed in Table 1. The EMACC reports to the Director of the Office of Energy Research in his capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMACC terms of reference. In this report are described 1) EMACC activities for FY 1982; 2) a summary of materials funding in the Department from FY 1978 to the present; and 3) on-going materials programs in the Department.

  3. Predicting technology operational availability using technical maturity assessment

    International Nuclear Information System (INIS)

    Kenley, C.R.; Creque, T.R.

    1998-01-01

    A technical maturity assessment method was performed by systems engineers in collaboration with an advisory panel composed of team members from different Department of Energy sites and from different engineering and science disciplines. Various stabilization technologies were assessed annually as to their relative maturity and availability for use in stabilizing nuclear materials. After three years of assessments, several of the technologies are now components of operational systems. A regression analysis of the historical assessments was performed, and it was concluded that the numerical technical maturity score produced by a team of experts can provide a powerful predictor of the time remaining until the operational application of technologies

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

    International Nuclear Information System (INIS)

    Vitikainen, E.; Silfverberg, P.

    1985-01-01

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

  5. Energy Materials Coordinating Committee (EMaCC): Annual technical report, fiscal year 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1993 and describes the materials research programs of various offices and divisions within the Department. The program descriptions consist of a funding summary for each Assistant Secretary office and the Office of Energy Research, and detailed project summaries with project goals and accomplishments. The FY 1993 budget summary table for DOE Materials Activities in each of the programs is presented.

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

    International Nuclear Information System (INIS)

    1998-03-01

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

  7. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2003

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2004-10-18

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed.

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

    International Nuclear Information System (INIS)

    1997-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-08-01

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

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

    International Nuclear Information System (INIS)

    2001-08-01

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

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

    International Nuclear Information System (INIS)

    1996-12-01

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

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

    International Nuclear Information System (INIS)

    1997-05-01

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

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

    International Nuclear Information System (INIS)

    2000-03-01

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

  15. 75 FR 39974 - NASA Advisory Council; Space Operations Committee; Meeting

    Science.gov (United States)

    2010-07-13

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice: (10-074)] NASA Advisory Council; Space... Committee of the NASA Advisory Council. DATES: Wednesday, July 28, 2010, 2-5 p.m. EDT. ADDRESSES: Doubletree..., Washington, DC 20546, 202/358-1507, [email protected]nasa.gov . SUPPLEMENTARY INFORMATION: The agenda for the...

  16. 75 FR 5630 - NASA Advisory Council; Space Operations Committee; Meeting

    Science.gov (United States)

    2010-02-03

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-017)] NASA Advisory Council; Space... Committee of the NASA Advisory Council. DATES: Wednesday, February 17, 2010, 9 a.m.-12 p.m. EST. ADDRESSES: NASA Headquarters, 300 E Street, SW., Washington, DC 20456, Room 2U22. FOR FURTHER INFORMATION CONTACT...

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

    International Nuclear Information System (INIS)

    2001-08-01

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

  18. External evaluation on Monju Core Confirmation Test in FY 2010 (the Technical Committee on Monju Research Utilization)

    International Nuclear Information System (INIS)

    2011-06-01

    This report describes the review made by the 'Technical Committee on Monju Research Utilization' on the results of Core Confirmation Test conducted from May to July in 2010. The committee consists of technical specialists in the relevant engineering domains from various Japanese industries and universities. The Committee was convened twice in 2010, in August and December, where the each item of the Core Confirmation Test was explained by individual personnel in charge, and the outline and the detailed analysis were discussed, respectively. Evaluations were made by the Committee after the questions and answers. Main points of the evaluations are listed below: After the 14 year stand-by, the Core Confirmation Test has been successfully completed within a brief duration of 3 months, with provision of precious technical data for future development and commercialization of FBRs. Safety has been confirmed and valuable data for analysis code validation have been acquired on an FBR core containing 1.5%wt of Am-241. It is significant that the newly released nuclear data library, JENDL-4.0 has been validated based on studies of capture cross section of Am-241 and of fission cross section of Pu-239. Finally, the chief examiner of the Committee stated his expectation for advancement of Japanese FBR technologies with the JAEA's leadership based of achievements on Monju, to be reflected on subsequent FBR developments. (author)

  19. Training of technical staff for nuclear power station operation

    International Nuclear Information System (INIS)

    Haire, T.P.; Myerscough, P.B.

    1981-01-01

    The statutory training requirements covering the technical staff in the CEGB (Central Electricity Generating Board) are discussed. Details of the training programmes emphasize the importance of the staff having a thorough understanding of the nuclear processes involved in the station operation and not relying solely upon a mechanistic approach to operating procedures. The impact of this philosophy on the design of training simulators is examined and a brief comparison is made with the training philosophies in other countries. (U.K.)

  20. RF Regional Technical Centers for MPC and A Sustainability Operations

    International Nuclear Information System (INIS)

    Lambert, L D; Toth, W J; Hendrickson, S

    2004-01-01

    The National Nuclear Security Administration (NNSA) programmatic vision to be a catalyst in Russia's assumption of responsibility for long-term system operation is exemplified in the sustainability cooperation with the RF Ministry of Defense (MOD). An identified goal for the MPC and A Program is to encourage the development of Russian Federation (RF) capabilities and commitments to operate and maintain safeguard improvements. The RF MOD Technical Support Center development fulfills the NNSA mission and MPC and A Program goal. The regional technical center concept involves a systematic approach to aid in the determination of the level of sustainability assistance required to transition operators, maintenance, training, and testing of MPC and A systems to the RF MOD. This paper describes the process used to create the RF MOD Technical support center. First are described the needs analyses conducted to determine the key system sustainability factors requiring support. These sustainability functions are then compiled to influence the form and ultimate physical design of the technical support center. Operational interfaces are described, in detail that show the benefit of the center to the individual sites. Finally, benefits relating to information accessibility and other economies of scale are described that highlight the central center concept's strengths

  1. 78 FR 1823 - Cable Television Technical and Operational Requirements

    Science.gov (United States)

    2013-01-09

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 79 [MB Docket No. 12-217; DA 12-2081] Cable Television Technical and Operational Requirements AGENCY: Federal Communications Commission. ACTION: Proposed rule; extension of reply comment period. SUMMARY: In this document, the Commission extends the deadline...

  2. 40th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-02)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 40th plenary on 9-13 July 2012 in Copenhagen (Denmark). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics...

  3. 39th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-01)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 39th plenary on 16-20 April 2012 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics...

  4. Turnaround operations analysis for OTV. Volume 2: Detailed technical report

    Science.gov (United States)

    1988-01-01

    The objectives and accomplishments were to adapt and apply the newly created database of Shuttle/Centaur ground operations. Previously defined turnaround operations analyses were to be updated for ground-based OTVs (GBOTVs) and space-based OTVs (SBOTVs), design requirements identified for both OTV and Space Station accommodations hardware, turnaround operations costs estimated, and a technology development plan generated to develop the required capabilities. Technical and programmatic data were provided for NASA pertinent to OTV round and space operations requirements, turnaround operations, task descriptions, timelines and manpower requirements, OTV modular design and booster and Space Station interface requirements. SBOTV accommodations development schedule, cost and turnaround operations requirements, and a technology development plan for ground and space operations and space-based accommodations facilities and support equipment. Significant conclusion are discussed.

  5. Independent technical review of the Hanford Tank Farm Operations

    International Nuclear Information System (INIS)

    1992-07-01

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

  6. 76 FR 2369 - Notice of Staff Attendance at Southwest Power Pool Markets and Operation Policy Committee and...

    Science.gov (United States)

    2011-01-13

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Notice of Staff Attendance at Southwest Power Pool Markets and Operation Policy Committee and Strategic Planning Committee Meetings January 5... the meetings of the Southwest Power Pool, Inc. (SPP) Markets and Operations Policy Committee (MOPC...

  7. Tribal Geographic Area (RTOC) Polygons with Representative Information, US EPA Region 9, 2015, Regional Tribal Operations Committee

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Regional Tribal Operations Committee (RTOC) is a working committee of EPA and Tribal personnel co-chaired by an EPA representative and a Tribal representative....

  8. Technical information report: Plasma melter operation, reliability, and maintenance analysis

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1995-01-01

    This document provides a technical report of operability, reliability, and maintenance of a plasma melter for low-level waste vitrification, in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. A process description is provided that minimizes maintenance and downtime and includes material and energy balances, equipment sizes and arrangement, startup/operation/maintence/shutdown cycle descriptions, and basis for scale-up to a 200 metric ton/day production facility. Operational requirements are provided including utilities, feeds, labor, and maintenance. Equipment reliability estimates and maintenance requirements are provided which includes a list of failure modes, responses, and consequences

  9. 41th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-03)

    DEFF Research Database (Denmark)

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

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

  10. Use of neutron beams for low and medium flux research reactors: Radiography and materials characterization. Report of a technical committee held in Vienna, 4-7 May 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The present report is the result of the Technical Committee meeting held during 4-7 May 1993 in Vienna, Austria, and includes contributions from the participants. The Physics Section of the Department of Research and Isotopes was responsible for the co-ordination and compilation of the report. The report is intended to provide guidelines to research reactor owners and operators for promoting and developing their research programmes and industrial applications for neutron radiology, related neutron inspection and analytical techniques and neutron beam irradiation. Refs, figs and tabs.

  11. Use of neutron beams for low and medium flux research reactors: Radiography and materials characterization. Report of a technical committee held in Vienna, 4-7 May 1993

    International Nuclear Information System (INIS)

    1995-10-01

    The present report is the result of the Technical Committee meeting held during 4-7 May 1993 in Vienna, Austria, and includes contributions from the participants. The Physics Section of the Department of Research and Isotopes was responsible for the co-ordination and compilation of the report. The report is intended to provide guidelines to research reactor owners and operators for promoting and developing their research programmes and industrial applications for neutron radiology, related neutron inspection and analytical techniques and neutron beam irradiation. Refs, figs and tabs

  12. Operating experience feedback report: Technical specifications: Commercial power reactors

    International Nuclear Information System (INIS)

    O'Reilly, P.D.; Plumlee, G.L. III.

    1989-03-01

    This report documents a trends and patterns analysis of technical specification (TS)-related licensee event reports (LERs) conducted by the Nuclear Regulatory Commission's (NRC's) Office for Analysis and Evaluation of Operational Data (AEOD). The objectives of this analysis were (1) to identify and catalog technical specification-related LERs, (2) to categorize and evaluate the events reported in these a LERs, (3) to identify any issues arising from the evaluation which appear to have generic safety significance, or which relate to the on-going Technical Specification Improvement Program, and (4) to trend the results obtained from the analysis of the data obtained in (1) through (3). 9 refs., 9 figs., 22 tabs

  13. Ergonomic requirements for the operation of machines and technical equipment

    Directory of Open Access Journals (Sweden)

    Górny Adam

    2017-01-01

    Full Text Available In order to operate machinery and equipment safely, it is critical for the solutions in place to conform to design-related and operating requirements. Design-related requirements are primarily the responsibility of machine designers/developers and manufacturers. Operating requirements should be satisfied by employers, who are responsible for ensuring safe working conditions for their employees. Under applicable laws, machinery and equipment should be designed, produced and then operated without placing excessive loads on workers and in keeping with machine functionality and intended use. One should also ensure that machinery and equipment can be maintained and adjusted without exposing their operators to hazards. Ergonomic criteria are an integral part of such requirements. They ensure that human users and operators of technical equipment are enabled to function properly. Design-related requirements are viewed as a priority safety consideration. While they facilitate the use of technical tools, the actual safety of employees ultimately depends on the satisfaction of specific requirements during operation.

  14. The Agency's Technical Co-operation activities in 1987. Report by the Director General

    International Nuclear Information System (INIS)

    1988-08-01

    This report is part of a wide range of documentation which the Agency provides to Member States on its technical co-operation activities at various times during the year. It is, in particular, complemented by the achievement reporting submitted to the Technical Assistance and Co-operation Committee of the Board in the annual implementation reports that give the status of the technical co-operation programmes as at 30 September in each year. Following the 1986 Technical Co-operation Seminar and based on continuing consultations with Member States various steps to improve the quality of the programme were taken in 1987: for example, new project request forms and management plans were introduced and preparatory assistance was expanded. Office automation was intensified and the computerized data base covering technical co-operation was enhanced further. Work continues on the adaptation of data provided by the new Financial Information and Control System (FIGS) to the needs of the technical co-operation programmes and vice-versa. While several problems have still to be overcome, it has on the whole, been possible in this report to re-establish data comparability with previous years. Evaluation has become an integral part of the Agency's technical cooperation activities. In addition to on-going mid-project and end-of-project evaluations, expert services and fellowships were evaluated in 1987 and the first country programme evaluation was also undertaken. During 1987, a total of 962 projects were operational and 64 training courses were held. These activities involved 1808 expert assignments while 1975 persons received training abroad. Of the provisions in the 1987 total adjusted programme, one half was earmarked for equipment, while the other half was equally divided between ear markings for experts and for training. Of the Agency's technical co-operation resources in 1987, 72.5% came from the Technical Assistance and Co-operation Fund, 13.7% from extra budgetary

  15. 200-UP-2 Operable Unit technical baseline report

    International Nuclear Information System (INIS)

    Deford, D.H.

    1991-02-01

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

  16. IAEA technical co-operation activities in the 1990s

    International Nuclear Information System (INIS)

    1995-01-01

    The desire to extend the many benefits of the peaceful uses of nuclear technology to all countries led as long ago as 1957 to the establishment of the IAEA and to immediate introduction of a technical co-operation programme. In the more than thirty years that have passed since that time, the potential applications of nuclear techniques have greatly expanded. Over the period, many of the applications have moved from research laboratories into hospitals, farms and industrial enterprises. The direct resources made available to the IAEA by its Member States to support technology transfer processes have grown rapidly since the late 1950s. The current trends in the technical co-operation activities of the IAEA and some examples of projects supported by the IAEA are briefly presented in this document

  17. IAEA technical co-operation and the NPT

    International Nuclear Information System (INIS)

    Velez Ocon, C.

    1985-01-01

    The IAEA technical co-operation programme promotes nuclear techniques and technologies in the developing countries. The Statute, the NPT, and the Revised Guiding Principles all reflect the desire of countries to foster an international climate where it will be unacceptable for a non-nuclear-weapon State to indulge in the development of military nuclear technology and reprehensible for States possessing this technology to offer it to others

  18. 75 FR 67345 - Agricultural Policy Advisory Committee for Trade and the Agricultural Technical Advisory...

    Science.gov (United States)

    2010-11-02

    ... balance on each committee will also be sought. Nominations: Nominating a person to serve on any of the... ability to serve as an advisor on the U.S. agriculture advisory committee for trade. Dated: October 26...

  19. Technical aspects of ageing for long-term operation

    International Nuclear Information System (INIS)

    2003-01-01

    The aspects of plant ageing management gained increasing attention over the last ten years. Numerous technical studies have been performed to study the impact of ageing mechanisms on the safe and reliable operation of nuclear power plants. National research activities have been initiated or are in progress to provide the technical basis for decision making processes. The long-term operation of nuclear power plants is influenced by economic considerations, the socio-economic environment including public acceptance, developments in research and the regulatory framework, the availability of technical infrastructure to maintain and service the systems, structures and components as well as qualified personnel. This document restricts itself to the technical aspects of the basis for long-term operation. Its objective is the characterisation of technical key items. Regulatory aspects are being discussed within CNRA. The light water reactor (LWR) nuclear power plants in operation are generically of pressurised water reactor (PWR) or boiling water reactor (BWR) type. The design principles of the nuclear steam supply system (NSSS) are proven in long-term operation as well as the principles being applied to the balance of plant (BOP), although a rather large variety of technical solutions do exist. The steps in the developments were tremendous in the 60's and 70's up to a power output of 1200 MWe followed by a period of further optimisation in the 80's and 90's, which raised it close to 1500 MWe. The NPPs in operation can be grouped into different generations of design in order to characterise similarities in technical principles and manufacturing standards. In the area of civil and mechanical structures and components there has been continuous development to optimise the design, the materials used as well as the manufacturing technology. The majority of these structures and components is still in use. In principle there are no major obstacles to further use of these

  20. 200-BP-5 operable unit Technical Baseline report

    International Nuclear Information System (INIS)

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

    1991-10-01

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

  1. 77 FR 23766 - Business and Operations Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2012-04-20

    ... of NSF's business operations. Agenda May 8, 2012 Welcome/Introductions; BFA/OIRM Overview; Challenges to Reduce Costs and Identify Efficiencies--Introduction, Panel/Discussion; Change Management/Effect... NATIONAL SCIENCE FOUNDATION Business and Operations Advisory Committee; Notice of Meeting In...

  2. 78 FR 29201 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2013-05-17

    ... the International Maritime Organization's (IMO) Marine Safety Committee to be held at the IMO... session of the Sub-Committee) Technical co-operation activities relating to maritime safety and security... amendments to mandatory instruments Measures to enhance maritime security Goal-based new ship construction...

  3. 77 FR 57638 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-09-18

    ... the International Maritime Organization's (IMO) Marine Safety Committee to be held at the IMO... seventeenth session of the Sub-Committee); Technical co-operation activities relating to maritime safety and... amendments to mandatory instruments; Measures to enhance maritime security; Goal-based new ship construction...

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

    International Nuclear Information System (INIS)

    1999-11-01

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

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

    International Nuclear Information System (INIS)

    1997-10-01

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

  6. Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

    International Nuclear Information System (INIS)

    1986-05-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions

  7. Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-05-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions.

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

    International Nuclear Information System (INIS)

    1998-11-01

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

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

    Science.gov (United States)

    1998-06-01

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

  10. Report on Defense Business Operations to the Congressional Defense Committees

    Science.gov (United States)

    2009-03-15

    Department’s strategic framework for planning and decision-making, and acknowledged the need to establish clear, actionable strategic goals and...Business Operations Department of Defense Business Transformation 5 2. Business Enterprise Priorities Six Business Enterprise Priorities ( BEPs ... framework products that facilitate the interoperability and integration of the operational activities, processes, data, information exchanges

  11. Outlook for the IAEA's technical co-operation programme

    International Nuclear Information System (INIS)

    Samiei, Massoud

    1998-01-01

    This is a slide presentation dealing with the following subjects: - the IAEA's programmes; - the technical co-operation programme; - past trends in the TC programme; - new initiatives in TC; - TC programme profile; - perspectives for the future. The major programmes conducted by IAEA are concerning: - nuclear power and fuel cycle; - nuclear applications; - nuclear, radiation and waste safety, nuclear verification and security material; - management of technical co-operation; - policy making, coordination and support. In relation with the IAEA role in development process the author presents the legal framework for TC, the programme structure, and programme areas, resources, budgets, cycle, approval and implementation. Two plots regarding the recipients with and without NPP's are displayed for the period 1980-1994. Also, according to the status of the member states (without and with nuclear power programme) the programme priorities are presented. For the first case these are: radiation and waste safety, food and agriculture, water resources management human health and nutrition, human resources development, environmental protection and industrial applications. For the second case there are mentioned: radiation and nuclear safety, nuclear power operation and maintenance management, radioactive waste management, environment protection and sustainable energy options. Concerning the regional distribution the following figures are given for 1997: West Asia, 9%; Europe, 18%; Inter-regional, 11%; Africa, 24%; Latin America, 21%; East Asia and Pacific, 17%. In conclusion, the hope is expressed that the value of Technical Co-operation Programme would be seen not only in the successful transfer of technology but also, in the way that the nuclear technologies may satisfy demands for sustainable development by having a lasting impact on the life of the majority in a cost effective and environmentally sound manner

  12. 43rd Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-13-01)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 43rd plenary on 8-12 July 2013 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics deal...... were inter alia assessments of the economic performance of the EU fishing fleet, fishing effort regime evaluations, future EU data collection, and review of stock advice.......The Scientific, Technical and Economic Committee for Fisheries hold its 43rd plenary on 8-12 July 2013 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics dealt...

  13. GANIL, Technical report on operating accelerators, 1995-1996

    International Nuclear Information System (INIS)

    Bex, M.

    1998-01-01

    This report covers the years 1995-1996 and presents the GANIL accelerator operation, the machine studies, the technical developments, the safety problems, the SISSI system and the THI project. The technical developments refer to: production of multicharged metallic ions by the association of an excimer laser and an ECR source; production of multicharged metallic ions with an ECR source by the sputtering method; detection of beam losses and safety system for these losses; rotating spiraled wire; renovation or RF systems; renovation of power supplies and NMR system; upgrade of GANIL control system cluster; adaptation of the GANIL control system to the SPIRAL project and control system for NMR probe measurements. Annexes giving the experiments performed in nuclear physics and in fast ion physics are given as well as a list of the beams accelerated together with their characteristics (charged state, frequency, final energy, intensity on target). Also added is a list of publications

  14. 44th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-13-03)

    DEFF Research Database (Denmark)

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

    The Scientific, Technical and Economic Committee for Fisheries hold its 44th plenary on 4-8 November 2013 in Brussels (Belgium). The terms of reference included both issues assessments of STECF Expert Working Group reports and additional requests submitted to the STECF by the Commission. Topics...... dealt were inter alia assessments of the economic performance of the EU aquaculture and fish processing sectors, fishing effort regime evaluations, and review of stock advice....

  15. 76 FR 20717 - NASA Advisory Council; Space Operations Committee; Meeting.

    Science.gov (United States)

    2011-04-13

    ...: Doubletree Hotel, 2080 North Atlantic Ave, Cocoa Beach, FL 32931. FOR FURTHER INFORMATION CONTACT: Mr. Jacob... for the meeting includes the following topics: --Space Operations Mission Directorate FY2012 Budget...

  16. [Assessment of the sonographer's knowledge on the second trimester ultrasound recommendations of the National Technical Committee of Ultrasound].

    Science.gov (United States)

    Matar, M; Picone, O; Dalmon, C; Ayoubi, J-M

    2013-09-01

    To evaluate the sonographers' knowledge of the National Technical Committee of Ultrasound's recommendations concerning second trimester ultrasound. Anonymous questionnaire was sent by e-mails containing 25 questions about demographic elements, the practice of second trimester ultrasound and the recommendations of the National Technical Committee of Ultrasound about second trimester ultrasound. Six hundred and eighty-four responses were obtained. Six hundred and fifty-three upon 684 (95%) of respondents practice second trimester ultrasound and 635 upon 653 (97%) know about the existence of the report of the National Technical Committee of Ultrasound. The rates of correct answers concerning recommended biometrical images vary between 97% for the biparietal diameter and head circumference, 98% for abdominal circumference and 100% for the femur length. While for morphological images, rates vary between 52% and 100%. A subgroup analysis (whether the respondents have already read the recommendations or not) showed that those who had read the recommendations have significantly better results than those who did not. Those who have already read the recommendations have better knowledge and global knowledge can be improved. National recommendations serve to promote a policy of quality assurance of ultrasound and may be used in medicolegal issues. The societies that make recommendations should more diffuse their work and practitioners should make effort to pursue the continuing medical education and to implement the recommendations. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

  17. Results of Scientific and Technical Supervision of Hydraulic Fracturing Operations

    Directory of Open Access Journals (Sweden)

    I.Kh. Makhmutov

    2017-11-01

    Full Text Available The paper presents actual results of the research conducted as part of a field pilot project which consisted in interpretation of minifrac test data and evaluation of the efficiency of the scientific and technical supervision of fracking operations. The research program involved 11 wells targeting Devonian terrigenous reservoirs. Minifrac tests in one perforation interval were performed only in seven wells, that is approximately in 64% of total well count. A reliable fracture closure estimate was obtained only in six wells (55%, beginning of pseudoradial flow was observed only in one well out of 11 wells (9%. Hence, conventional minifrac tests should be supplemented with other diagnostic injection tests. Analysis of the performance of hydraulic fracturing operations conducted according to this pilot project plan indicates that fracture modelling, and scientific and technical supervision of fracking operations performed by Hydrofrac Research Laboratory of Institute TatNIPIneft Tatneft PJSC have yielded beneficial effects, namely 1.44 times increase in oil production rates.

  18. 21 CFR 14.80 - Qualifications for members of standing policy and technical advisory committees.

    Science.gov (United States)

    2010-04-01

    ... with interested organizations. Nonvoting members— (i) Shall be selected by the interested organizations... cause. Good cause includes excessive absenteeism from committee meetings, a demonstrated bias that...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-01

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

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

    International Nuclear Information System (INIS)

    2001-04-01

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

  1. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2004

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2005-08-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  2. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2002

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2003-08-08

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The EMaCC Charter and the memorandum approving it are presented in the Appendix of this report. The FY 2002 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2002 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2002 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  3. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2005

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2006-09-29

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  4. PARAMETRIC DIAGNOSTICS OF THE CENTRIFUGAL SUPERCHARGER'S TECHNICAL CONDITION DURING OPERATION

    Directory of Open Access Journals (Sweden)

    Regina A. Khuramshina

    2017-01-01

    Full Text Available Abstract. Objectives The main aim is to develop a mathematical model of a centrifugal compressor and carry out a parametric diagnostics of a centrifugal supercharger's technical condition during operation. Methods  A model is proposed for calculating the thermodynamic properties of natural gas, reducing the parameters of a centrifugal compressor to the initial conditions and to the rotation frequency, as well as the integral indicators of the supercharger's technical state. The technical state of the gas path of the centrifugal supercharger of the compressor unit is determined by the parametric diagnostic method. Results  The software implementation of the mathematical model of centrifugal compressor is carried out using a DVIGwT PC. The analysis of calculations indicates that the model is appropriate, with the error being due to taking into account the properties of iso-butane and i-hexane, in contrast with the VNIIGAZ technique. The evaluation studies of a centrifugal compressor's state are indicative of the presence or absence of its defects. Conclusion  Among a number of the diagnostic methods for evaluating a centrifugal supercharger, the most effective is vibrodiagnostics. However, the search for malfunctions and nascent defects in the flowing part of the centrifugal compressor cannot be limited only to vibrodiagnostic data, which provides about 60% of the reliable information about the state of the gas-air tract. About 20% of the compressor's malfunctions and approximately half of the dangerous modes of the supercharger's flow-through part is detected using thermogasdynamic parametric analysis (parametric diagnostics. The main difficulty of the control over the technical state of the flow-through part of the centrifugal supercharger is in the complication of the quantitative evaluation of the processes taking place in the supercharger, which leads to problems in providing reliable diagnosis during a reasonable period of time.

  5. MDEP Position Paper - PP-STC-01 - MDEP Steering Technical Committee Position Paper on Safety Goals

    International Nuclear Information System (INIS)

    2011-01-01

    In considering the acceptability of a nuclear facility in relation to safety, Governments and regulatory bodies define a range of legal, mandatory requirements which are supplemented by regulatory requirements and expectations which may not have a mandatory nature. The term 'safety goals' is used to cover all health and safety requirements and expectations which must be met: these may be deterministic rules and/or probabilistic targets. They should cover the safety of workers, public and the environment in line with the IAEA's Basic Safety Objective encompassing safety in normal operation through to severe plant states. Although all regulators have safety goals, these are expressed in many different ways and exercises in comparing them frequently are done at a very low level e.g. specific temperature limits in the reactor core. The differences in the requirements from different regulators are difficult to resolve as the goals are derived using different principles and assumptions and are usually for a specific technology. Therefore the Multinational Design Evaluation Programme (MDEP) set up a sub-committee to investigate a different approach. This approach was to start with the high level safety goals and try to derive a structure and means of deriving lower level safety goals that can be seen to be clearly related to the higher level ones. The work will greatly assist in the process of harmonisation of regulatory requirements and enhance coherence and consistency between goals for different technologies. MDEP expects that higher levels of safety will be achieved in the design and operation of new reactors. MDEP strongly supports the structure of safety goals and targets, as set out in this paper, for consideration of its members and IAEA and other organisations, in moving towards international harmonisation of regulatory requirements. MDEP strongly supports the use of integrated decision-making for design evaluation and operational safety. MDEP recognises the need

  6. Report to NASA Committee on Aircraft Operating Problems Relative to Aviation Safety Engineering and Research Activities

    Science.gov (United States)

    1963-01-01

    The following report highlights some of the work accomplished by the Aviation Safety Engineering and Research Division of the Flight Safety Foundations since the last report to the NASA Committee on Aircraft Operating Problems on 22 May 1963. The information presented is in summary form. Additional details may be provided upon request of the reports themselves may be obtained from AvSER.

  7. Technical Advisory Committee on the nuclear fuel waste management program : thirteenth annual report

    International Nuclear Information System (INIS)

    Shemilt, L.W.

    1993-03-01

    Since the last reporting period by the Technical Advisory Committee (TAC) the emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of nine primary reference documents as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO). The disposal concept developed over the last fourteen years by Atomic Energy of Canada Limited (AECL) and anticipated to be presented by means of the EIS in 1994, is based on a multiple system of natural and man-made barriers wherein nuclear waste is first enclosed in corrosion-resistant containers, designed to last at least 500 years, and then placed in a vault excavated 500 - 1000 m deep in granitic rocks of the Canadian Shield. After container emplacement either in or on the floor of the vault, and with a surrounding buffer material of a bentonite clay/sand mixture, the vault will be backfilled and sealed with crushed rock, buffer and sand, as will be the shafts and exploratory boreholes. The case study being presented by AECL to demonstrate the safety of this concept and the technology to implement it, relies on computer simulations of a hypothetical disposal site with geological characteristics similar to those at the Underground Research Laboratory (URL) in the Whiteshell Research Area (WRA) located in Manitoba. The preliminary simulation results suggest that safe containment can be achieved provided that the waste is surrounded by a sparsely-fractured zone of rock wherein movement of contaminants carried by groundwater is modelled as a diffusive as opposed to a advective process. The principal focus of work during the past year within the environmental and safety assessment has been to complete the Post

  8. International co-operation through scientific and technical nuclear societies

    International Nuclear Information System (INIS)

    Manning Muntzing, L.

    1983-01-01

    As an international organization the American Nuclear Society (ANS) has played an active role in international co-operation of nuclear technology exchange since its establishment in 1954. The ANS has a membership of over 13,000 individuals, of whom approximately 1200 live overseas in forty countries. To carry out the goals of the Society, local sections have been established. Currently the ANS maintains 48 local sections in the United States of America and 8 overseas local sections in Africa, Asia, Europe and South America. The ANS also has formal agreements for co-operation with The Asociacion Argentina de Tecnologia Nuclear (AATN), the Israel Nuclear Society (INS), and the Chinese Nuclear Society (CNS). In 1977 the Japan Atomic Energy Society (JAES), the European Nuclear Society (ENS), and the ANS co-operation in sponsoring the First International Conference on Transfer of Nuclear Technology (ICONTT I) in Tehran, Iran. In 1982, the Second International Conference on Transfer of Nuclear Technology (ICONTT II), Buenos Aires, Argentina, was sponsored through the co-operation of the AATN, the ENS and the ANS. The ANS and its overseas sections sponsor the Pacific Basin Conference approximately every three years to discuss nuclear matters of concern to the countries around the Pacific Ocean. In 1981 the ANS held a Nuclear Technology Exhibit in Beijing, the People's Republic of China. In addition to meetings, the ANS is extensively involved in the co-operative exchange of applied nuclear research information through its publications. Nuclear Technology, a technical journal, is published monthly under joint ownership of the ENS and the ANS. The ANS has been a leader in voluntary standards development since 1958. In its dedication to the co-operation of international nuclear technology the ANS maintains a comprehensive international exchange of nuclear standards

  9. Occupational exposure to ambient electromagnetic fields of technical operational personnel working for a mobile telephone operator

    International Nuclear Information System (INIS)

    Chauvin, S.; Gibergues, M. L.; Wuethrich, G.; Picard, D.; Desreumaux, J. P.; Bouillet, J. C.

    2009-01-01

    In order to investigate the exposure of operational personnel to radiofrequency electromagnetic fields when working for a mobile telephone operator, exposimeters were used to make individual records on 23 Technical Operations personnel (mobile telephone maintenance staff) and also on 22 Other Workers. The exposure densities, to which each of the 45 subjects was subjected, were quantified using 229 exposure indicators. Cluster analysis techniques were applied to the data, in an attempt to show that they would re-emerge as belonging to one of the two groups, i.e. the Technical Operational Personnel group or the Other Workers group. This exploratory investigation has shown that the cluster analysis does not reveal a sufficiently reliable emergence of the two groups, even though certain exposure indicators were significantly different for the two groups. In addition, the use of a Learning Group method does not lead to the discovery of a predictive law that could identify the Technical Operational Personnel as a sub-group within the overall group. (authors)

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

    International Nuclear Information System (INIS)

    2010-10-01

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

  11. Independent Electricity Market Operator integration management participant technical reference manual

    International Nuclear Information System (INIS)

    1999-01-01

    The document provides potential participants with the essential technical information to permit them to participate in the IMO-administered markets, and is not intended to be a complete technical reference manual for all issues within the realm of electricity production, distribution, or consumption. Written for the participants, it provides only that information which is relevant to the participant for interfacing with the IMO and participating in the market. Written as a generic guide, all the information contained within it may not be relevant to all the participants. The document's intent is to provide participants with a description of the various facilities and interfaces required by market participants to take part in the IMO-administered markets. The document supplements the market rules and provides installation, set-up, and configuration information for the various tools and facilities that will be required for market participation as a supplier, carrier/delivery (transmitter/distributor), generator, or consumer in the market. Aspects considered include: participant workstation specifications, dispatch workstation specification, message exchange, remote terminal unit specification, AGC operational RTU specification, real time network connection specification, telephone connection specification, revenue administration specification, funds administration specification, data catalogues, market information, power grid connection requirements, and appendices

  12. Technical innovations at NPP Dukovany - for safe and efficient operation

    International Nuclear Information System (INIS)

    Sabata, M.; Vasa, I.

    2000-01-01

    Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

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

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1983-05-01

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

  14. 75 FR 1339 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2010-01-11

    ...), Building 33, Cloud Room, 53560 Hull Street, San Diego, California 92152. The Committee advises the Office... Session 1. Welcome and Introduction. 2. Working Groups Reports. 3. Industry Presentations. 4. New Business...

  15. 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...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

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

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

    International Nuclear Information System (INIS)

    1995-11-01

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

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

    International Nuclear Information System (INIS)

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

    2010-02-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1998-09-01

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

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

    International Nuclear Information System (INIS)

    1999-12-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

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

  5. AGU Committees

    Science.gov (United States)

    Administrative Committees are responsible for those functions required for the overall performance or well-being of AGU as an organization. These committees are Audit and Legal Affairs, Budget and Finance*, Development, Nominations*, Planning, Statutes and Bylaws*, Tellers.Operating Committees are responsible for the policy direction and operational oversight of AGU's primary programs. The Operating Committees are Education and Human Resources, Fellows*, Information Technology, International Participation*, Meetings, Public Affairs, Public Information, Publications*.

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

    International Nuclear Information System (INIS)

    1997-09-01

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

  7. Ergonomic guidelines for using notebook personal computers. Technical Committee on Human-Computer Interaction, International Ergonomics Association.

    Science.gov (United States)

    Saito, S; Piccoli, B; Smith, M J; Sotoyama, M; Sweitzer, G; Villanueva, M B; Yoshitake, R

    2000-10-01

    In the 1980's, the visual display terminal (VDT) was introduced in workplaces of many countries. Soon thereafter, an upsurge in reported cases of related health problems, such as musculoskeletal disorders and eyestrain, was seen. Recently, the flat panel display or notebook personal computer (PC) became the most remarkable feature in modern workplaces with VDTs and even in homes. A proactive approach must be taken to avert foreseeable ergonomic and occupational health problems from the use of this new technology. Because of its distinct physical and optical characteristics, the ergonomic requirements for notebook PCs in terms of machine layout, workstation design, lighting conditions, among others, should be different from the CRT-based computers. The Japan Ergonomics Society (JES) technical committee came up with a set of guidelines for notebook PC use following exploratory discussions that dwelt on its ergonomic aspects. To keep in stride with this development, the Technical Committee on Human-Computer Interaction under the auspices of the International Ergonomics Association worked towards the international issuance of the guidelines. This paper unveils the result of this collaborative effort.

  8. 78 FR 18578 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2013-03-27

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Hydrogen and Fuel Cell... Energy. ACTION: Notice of Open Meeting. SUMMARY: This notice announces an open meeting of the Hydrogen... Avenue, Washington, DC 20585. SUPPLEMENTARY INFORMATION: Purpose of the Committee: The Hydrogen and Fuel...

  9. 76 FR 28759 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

    Science.gov (United States)

    2011-05-18

    ...), Public Law 109-58; 119 Stat. 849. The Federal Advisory Committee Act, Public Law 92-463, 86 Stat. 770... Rochester Airport Hotel, 1890 Ridge Road West, Rochester, New York. FOR FURTHER INFORMATION CONTACT: Send... procedures, members of the public are welcome to observe the business of the meeting of HTAC and to make oral...

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

    International Nuclear Information System (INIS)

    2001-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

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

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

    International Nuclear Information System (INIS)

    2000-07-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  14. A review of IAEA's technical co-operation programme

    International Nuclear Information System (INIS)

    Samiei, M.

    2004-01-01

    Full text: The Technical Co-operation (TC) Programme is part of the Agency's mandate 'to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' The IAEA's role under this Programme is that of a scientific and technical agency making a discrete but significant contribution to sustainable development goals through the transfer of nuclear science and technology. TC is a high impact programme focusing on development needs with about 800 active projects annually with a budget of over $70M, 30% of which is targeted on training and capacity building in over 100 Member States. Since 1970, over 80,000 scientists and specialists from developing countries have been trained in nuclear science and technology and in nuclear power and safety. A number of trends in the world at large will be likely to influence the Agency's TC programme in the next several years: The use of nuclear technologies in developing countries is growing as local infrastructures improve and technology transfer increases, especially among developing countries; Some countries and institutions are becoming more self-reliant as viable markets develop for nuclear technology, based on an increased awareness of their benefits; As facilities age, safe strategies for life extension and for decommissioning are assuming increasing importance, while there is some renewed positive attention to nuclear power in several parts of the world. Concern is increasing related to the potential for malicious acts involving nuclear facilities or unsecured nuclear and other radioactive material. As the nuclear workforce ages, the management of nuclear knowledge is gaining increasing importance, including the need to maintain the safety and security of nuclear installations and their continued reliable operation. It is difficult to forecast precisely how these trends will influence the assistance requested by Member States, but it is already clear that there will be increased

  15. The Agency's technical co-operation activities in 1993

    International Nuclear Information System (INIS)

    1994-08-01

    This document reviews the IAEA's Technical Cooperation activities for 1993. Apart from an overview, the report contains reviews by Agency programmes and technical divisions, by area, by component and by fund. Summaries of project implementation are also included, as well as indications of the achievements of projects completed in 1993

  16. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  17. 76 FR 17143 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2011-03-28

    ... Data System 5. Enhancing Air Cargo Security 6. National Strategy Global Supply Chain Security and the...: Committee Management; Notice of Federal Advisory Committee Meeting. SUMMARY: The Advisory Committee on...

  18. 76 FR 58030 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2011-09-19

    ... steps and formulate recommendations on the following four issues: The work of the Global Supply Chain...: Committee Management; Notice of Federal Advisory Committee Meeting. SUMMARY: The Advisory Committee on...

  19. A regulator's perspective on NRC's participation in the operations ampersand maintenance committees

    International Nuclear Information System (INIS)

    Wessman, R.H.

    1996-01-01

    As a regulator fairly new to the American Society of Mechanical Engineers (ASME) Operations and Maintenance (O ampersand M) Committee process, the author does not have a personal historical perspective as do many of the longer-term, and highly respected, members of the O ampersand M Committee. However, as Branch Chief of the Mechanical Engineering Branch, Division of Engineering, in the Office of Nuclear Reactor Regulation at the NRC for just over two years, he has responsibility for the regulatory agency's review of licensee actions involving the products that come from the efforts of the O ampersand M Committee, as well as responsibility for portions of the activities of interest to other ASME Code groups such as Section III, Section XI, and Qualification of Mechanical Equipment. As a result, the author has learned a great deal about the code process in a short time. Here he gives his perspectives on the process and provides a few thoughts on the direction for the future

  20. A regulator`s perspective on NRC`s participation in the operations & maintenance committees

    Energy Technology Data Exchange (ETDEWEB)

    Wessman, R.H.

    1996-12-01

    As a regulator fairly new to the American Society of Mechanical Engineers (ASME) Operations and Maintenance (O&M) Committee process, the author does not have a personal historical perspective as do many of the longer-term, and highly respected, members of the O&M Committee. However, as Branch Chief of the Mechanical Engineering Branch, Division of Engineering, in the Office of Nuclear Reactor Regulation at the NRC for just over two years, he has responsibility for the regulatory agency`s review of licensee actions involving the products that come from the efforts of the O&M Committee, as well as responsibility for portions of the activities of interest to other ASME Code groups such as Section III, Section XI, and Qualification of Mechanical Equipment. As a result, the author has learned a great deal about the code process in a short time. Here he gives his perspectives on the process and provides a few thoughts on the direction for the future.

  1. Activities of RILEM Technical Committee: Internal Curing of Concrete and Anticipated Research

    DEFF Research Database (Denmark)

    Kovler, Konstantin; Jensen, Ole Mejlhede

    in the domain. To account for the different practices and different standards around the world, the TC included representatives from three different world regions: Europe, North America and Asia. Totally more than 30 members from 17 countries contributed in the committee work. Some of them serve in parallel...... of Concrete” of the International Union of Laboratories and Experts in Construction Materials, Systems and Structures (RILEM). The authors of this short communication served as a chair (K. Kovler) and secretary (O.M. Jensen) of the TC. The regular and corresponding members were acknowledged RILEM experts...

  2. Energy Materials Coordinating Committee (EMaCC). Annual Technical Report, Fiscal Year 2000

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2001-07-31

    The Energy Materials Coordinating Committee Annual Report (attached, DOE/SC-0040) provides an annual summary of non-classified materials-related research programs supported by various elements within the Department of Energy. The EMaCC Annual Report is a useful working tool for project managers who want to know what is happening in other divisions, and it provides a guide for persons in industry and academia to the materials program within the Department. The major task of EMaCC this year was to make the Annual Report a more user-friendly document by removing redundant program information and shortening the project summaries.

  3. Bio-aggregates based building materials state-of-the-art report of the RILEM Technical Committee 236-BBM

    CERN Document Server

    Collet, Florence

    2017-01-01

    The work of the RILEM Technical Committee (TC -236 BBM) was dedicated to the study of construction materials made from plant particles. It considered the question whether building materials containing as main raw material recyclable and easily available plant particles are renewable. This book includes a state-of-the-art report and an appendix. The state-of-the-art report relates to the description of vegetal aggregates. Then, hygrothermal properties, fire resistance, durability and finally the impact of the variability of the method of production of bio-based concrete are assessed. The appendix is a TC report which presents the experience of a working group. The goal was to define testing methods for the measurement of water absorption, bulk density, particle size distribution, and thermal conductivity of bio aggregates. The work is based on a first round robin test of the TC-BBM where the protocols in use by the different laboratories (labs) are compared. .

  4. Current situation of International Organization for Standardization/Technical Committee 249 international standards of traditional Chinese medicine.

    Science.gov (United States)

    Liu, Yu-Qi; Wang, Yue-Xi; Shi, Nan-Nan; Han, Xue-Jie; Lu, Ai-Ping

    2017-05-01

    To review the current situation and progress of traditional Chinese medicine (TCM) international standards, standard projects and proposals in International Organization for Standardization (ISO)/ technical committee (TC) 249. ISO/TC 249 standards and standard projects on the ISO website were searched and new standard proposals information were collected from ISO/TC 249 National Mirror Committee in China. Then all the available data were summarized in 5 closely related items, including proposed time, proposed country, assigned working group (WG), current stage and classifification. In ISO/TC 249, there were 2 international standards, 18 standard projects and 24 new standard proposals proposed in 2014. These 44 standard subjects increased year by year since 2011. Twenty-nine of them were proposed by China, 15 were assigned to WG 4, 36 were in preliminary and preparatory stage and 8 were categorized into 4 fifields, 7 groups and sub-groups based on International Classifification Standards. A rapid and steady development of international standardization in TCM can be observed in ISO/TC 249.

  5. Solid State Sciences Committee (SSSC). Technical progress report, May 1, 1992--April 30, 1993

    International Nuclear Information System (INIS)

    Taylor, R.

    1995-01-01

    The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WMF)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also were developed for a study on neutron science, however, further activity is pending. A proposed study on ultrasmall devices has been expanded and absorbed into a broader context; the BPA, with SSSC participation, is preparing to hold a program initiation meeting to evaluate the need for a study on information technology and hardware

  6. Technical progress report to the Department of Energy on the Solid State Sciences Committee (SSSC)

    International Nuclear Information System (INIS)

    1995-01-01

    The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WNM)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also have been developed for studies on neutron scattering science, on ultrasmall devices, and on molecular routes to materials

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

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1953-07-24

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

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

    International Nuclear Information System (INIS)

    1997-11-01

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

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

    International Nuclear Information System (INIS)

    2004-10-01

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

  10. FEMA's purchase of a radiological training package: an avoidable disaster. Twenty-Third Report by the Committee on Government Operations, Ninety-Ninth Congress, First Session, House Report 99-367, November 12, 1985

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    A congressional study of allegations against the Federal Emergency Management Agency (FEMA) management of a training program to prepare for a transportation emergency involving radioactive materials focused on contracting procedures. The study uncovered a lack of concern on the part of the agency in its response to committee inquiries and hearings. The findings fault FEMA for noncompetitive procurement, ignoring the advice of a scientific interagency, poor training and operating procedures, and other failures involving the Bradford training package. The committee recommends a thorough review of contracting procedures and an improved relationship with the radiological technical advisors

  11. Energy Materials Coordinating Committee (EMACC). Annual Technical Report, Fiscal Year 1978

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1978-08-01

    The Department of Energy Materials Coordinating Committee (EMACC) completed its first year of activity in FY 1978. A major project during the year was to conduct a survey of topical areas and prepare the report, Survey and Analysis of Selected Topics within the Department of Energy's Materials Research and Development Programs. Seven topics selected were those that had a high level of Divisional interest and supplement those reported in FY 1977 in DOE/ET-0006. The topics and the EMACC panel leaders in charge of compiling information were: 1. Joining of Materials, E.E. Hoffman and E. Dalder; 2. Elastomers R. Nelson; 3. Catalysts and Catalytic Effects R. Epple; 4. Radiation Effects K. Zwilsky; 5. Superconductivity W. Clinton; 6. Cement and Concrete L. Kukacka BNL/R. Reeber; and 7. Alternate Materials R.R. Reeber The report summarizes over 250 projects in these areas and completes the initial review started by James Swisher FY 1977 EMACC Chairman.

  12. Energy materials coordinating committee (EMACC) Fiscal Year 1980. Annual technical report

    International Nuclear Information System (INIS)

    1980-01-01

    This report contains information on the FY 1980 Department of Energy materials research and development programs and on those programs/projects with a significant materials activity. It was compiled by the Energy Materials Coordinating Committee (EMaCC). The previous report in this series summarized the FY 1979 programs (DOE/US-0002-2). The report is separated into sections, each containing programs reporting to one of six Assistant Secretaries of the Department: Conservation and Solar Energy, Defense Programs, Environment, Fossil Energy, Nuclear Energy, and Resource Applications; and one section, Energy Research, responsible to the Director of the Office of Energy Research. For convenience in locating the generic types of materials activities, an Appendix has been added that contains a primary keyword index

  13. Energy materials coordinating committee (EMACC) Fiscal Year 1980. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    This report contains information on the FY 1980 Department of Energy materials research and development programs and on those programs/projects with a significant materials activity. It was compiled by the Energy Materials Coordinating Committee (EMaCC). The previous report in this series summarized the FY 1979 programs (DOE/US-0002-2). The report is separated into sections, each containing programs reporting to one of six Assistant Secretaries of the Department: Conservation and Solar Energy, Defense Programs, Environment, Fossil Energy, Nuclear Energy, and Resource Applications; and one section, Energy Research, responsible to the Director of the Office of Energy Research. For convenience in locating the generic types of materials activities, an Appendix has been added that contains a primary keyword index.

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

    Energy Technology Data Exchange (ETDEWEB)

    Evans, L.C.

    1955-01-18

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

  15. Energy Materials Coordinating Committee (EMaCC) annual technical report, fiscal year 1984 with fiscal year 1985 data

    Energy Technology Data Exchange (ETDEWEB)

    None

    1985-07-01

    The Department of Energy funded about 374 million dollars of materials science and technology activities in both fiscal years 1984 and 1985. These funds and the commensurate program management responsibilities resided in 21 DOE program offices, each of which has its own mission and responsibilities. The Energy Materials Coordinating Committee (EMaCC) provides a formal mechanism to insure coordinated planning and maximum programmatic effectiveness for the Department's 374 million dollar per year materials effort. The EMaCC reports to the Director of the Office of Energy Research who in turn has oversight responsibilities for proper coordination of the technical programs of the Department. In carrying out this responsibility, EMaCC hosts meetings, organizes working groups, and publishes an annual technical report. This report is mandated by the EMaCC Terms of Reference. Its purpose is to disseminate information on the DOE materials programs for more effective coordination. It describes the materials research programs of various offices and divisions within the Department for FY 1984, contains funding information for FYs 1984 and 1985, and summarizes EMaCC activities for FY 1985.

  16. Energy Materials Coordinating Committee (EMaCC) annual technical report, fiscal year 1984 with fiscal year 1985 data

    International Nuclear Information System (INIS)

    1985-07-01

    The Department of Energy funded about 374 million dollars of materials science and technology activities in both fiscal years 1984 and 1985. These funds and the commensurate program management responsibilities resided in 21 DOE program offices, each of which has its own mission and responsibilities. The Energy Materials Coordinating Committee (EMaCC) provides a formal mechanism to insure coordinated planning and maximum programmatic effectiveness for the Department's 374 million dollar per year materials effort. The EMaCC reports to the Director of the Office of Energy Research who in turn has oversight responsibilities for proper coordination of the technical programs of the Department. In carrying out this responsibility, EMaCC hosts meetings, organizes working groups, and publishes an annual technical report. This report is mandated by the EMaCC Terms of Reference. Its purpose is to disseminate information on the DOE materials programs for more effective coordination. It describes the materials research programs of various offices and divisions within the Department for FY 1984, contains funding information for FYs 1984 and 1985, and summarizes EMaCC activities for FY 1985

  17. IAEA technical co-operation with least developed Member States. Special evaluation

    International Nuclear Information System (INIS)

    1993-01-01

    The main purposes of this evaluation were to: Review the overall situation with regard to IAEA technical co-operation with least developed Member States, including specific conditions in nuclear-related activities prevailing in these countries, approaches and practices used by the IAEA in providing assistance to LDCs, and the main results of the co-operation in question. Identify any adjustments to technical co-operation with LDC Member States that may strengthen this activity

  18. Emergency Management Operations Process Mapping: Public Safety Technical Program Study

    Science.gov (United States)

    2011-02-01

    services Operational Activity Collect and Manage Cash Donations Once activated, refer cash donations to appropriate voluntary organizations...recovery operations. Operational Activity Conduct Euthanasia /Disposal Provide humane methods to euthanize affected animals to stop the spread of the...issue stop movement orders, and initiate animal vaccination and treatment programs, euthanasia efforts, or other protective measures designed to control

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    1995-09-01

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

  1. Technical co-operation report for 2000. Report by the Director General

    International Nuclear Information System (INIS)

    2001-01-01

    This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators

  2. Technical co-operation report for 2000. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report covers three separate topics. Part one fulfills the Agency's obligation under the General Conference resolution GC(44)/RES/18 to report on the Strengthening of Technical Co-operation. It covers the period from 1 April 2000 to 31 March 2001. The report examines the finalization of the 2001-2002 technical co-operation programme and several key concepts of the Technical Co-operation Strategy such as Partners in Development, Technical Co-operation among Developing Countries, and the continuing evolution of Regional Resource Centres. Reflecting an important trend in the technical co-operation programme, which was mandated by the General Conference, the report describes the results achieved in several programmes in least developed countries. Part two reports on the major achievements of the technical co-operation programme in 2000 in the different regions of the world. Part three presents a summary of the financial and non-financial parameters of the technical co-operation programme. The supplement to the report provides a more detailed review of resources and contributions, disbursements and non-financial indicators.

  3. 77 FR 31325 - National Fire Codes: Request for Comments on NFPA Technical Committee Reports

    Science.gov (United States)

    2012-05-25

    ... Fire Protection of Commercial Cooking Operations. NFPA 130 Standard for Fixed Guideway P Transit and... Apparatus P Driver/Operator Professional Qualifications. NFPA 1021 Standard for Fire Officer P Professional Qualifications. NFPA 1026 Standard for Incident P Management Personnel Professional Qualifications. NFPA 1031...

  4. 77 FR 47490 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-08-08

    ...: --Adoption of the agenda --Decisions of other IMO bodies --Global Maritime Distress and Safety System (GMDSS... facilities --Consideration of operational and technical coordination provisions of maritime safety... Vice-Chairman for 2014 --Any other business --Report to the Maritime Safety Committee Members of the...

  5. 77 FR 72431 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-12-05

    ... other IMO bodies --Global Maritime Distress and Safety System (GMDSS): --Review and modernization of the... operational and technical coordination provisions of maritime safety information (MSI) services, including the... business --Report to the Maritime Safety Committee Members of the public may attend this meeting up to the...

  6. Operation and maintenance of the technical installations in buildings

    DEFF Research Database (Denmark)

    Nielsen, O.(red.)

    The report contains twelve papers from a seminar on operation and maintenance, held at the Danish Building Research Institute in October 1976. The papers deal, among other things, with dimensioning and balancing of pipesystems, design of ventilating systems for adequate operation and maintenance,......, cost and quality in maintenance, maintenance service companies, as well as organization and training for building services maintenance....

  7. 76 FR 46312 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2011-08-02

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. USCBP-2011-0024] Advisory Committee on Commercial... Homeland Security (DHS). ACTION: Committee management; notice of Federal Advisory Committee meeting...-of-business on August 12, 2011. ADDRESSES: The meeting will be held at the Westin Long Beach Hotel...

  8. [Current value, technic and indications for obstetrical operations].

    Science.gov (United States)

    Bayer, H

    1983-01-01

    Starting point of this survey is the 1954 paper about obstetrical operations from H. Kraatz. It is demonstrated, that there were and there are defined principles, which continue to exist unchanged. They are the fundamentals of indication and technique of operations in obstetrics. Nevertheless there are distinct changes, too, caused by two factors, progress in medicine (development of antibiotics, anaesthesiology and neonatology) as well as change of aspect in obstetrics (e.g. toxemias of pregnancy, preterm labour). The methods are discussed in detail. Operations by vaginal route come in the foreground in the last years more again. They should be preferred in maternal interest. The enlarged indication for caesarean section was not able to succeed on a large scale. An uniform procedure is proposed both in cephalic and breech presentation, and the new formulated preconditions to these operations are discussed. All three techniques two abdominal ones and one vaginal one) are demanded in caesarean sections, because they come into question in special situations. There is a change in operative indications in cases of bleeding, because of an early diagnosis by ultrasound. The qualification and experience of the obstetrician is more decisive than the selected method of operation or the instrument's type. Therefore there should not be any cut in instruction and training. The versatility of operative technique is a prerequisite to a qualified indication.

  9. Environmental management system for transportation maintenance operations : [technical brief].

    Science.gov (United States)

    2014-04-01

    This report provides the framework for the environmental management system to analyze : greenhouse gas emissions from transportation maintenance operations. The system enables user : to compare different scenarios and make informed decisions to minim...

  10. Annual meeting on nuclear technology 1980. Technical meeting: Operating experiences

    International Nuclear Information System (INIS)

    1980-01-01

    In addition to general experiences, experiences in reactor operation with relation to the Phenix reactor, KNK-2 reactor, the AVR reactor, the BWR-type KKI-reactor, the Philippsburg-1 reactor and the Obrigheim reactor are described. (DG) [de

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

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

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

    International Nuclear Information System (INIS)

    2000-05-01

    Worldwide there is considerable experience in nuclear power technology, especially in water cooled reactor technology. Of the operating plants, in September 1998, 346 were light water reactors (LWRs) totalling 306 GW(e) and 29 were heavy water reactors (HWRs) totalling 15 GW(e). The accumulated experience and lessons learned from these plants are being incorporated into new advanced reactor designs. Utility requirements documents have been formulated to guide these design activities by incorporating this experience, and results from research and development programmes, with the aim of reducing costs and licensing uncertainties by establishing the technical bases for the new designs. Common goals for advanced designs are high availability, user-friendly features, competitive economics and compliance with internationally recognized safety objectives. Large water cooled reactors with power outputs of 1300 MW(e) and above, which possess inherent safety characteristics (e.g. negative Doppler moderator temperature coefficients, and negative moderator void coefficient) and incorporate proven, active engineered systems to accomplish safety functions are being developed. Other designs with power outputs from, for example, 220 MW(e) up to about 1300 MW(e) which also possess inherent safety characteristics and which place more emphasis on utilization of passive safety systems are being developed. Passive systems are based on natural forces and phenomena such as natural convection and gravity, making safety functions less dependent on active systems and components like pumps and diesel generators. In some cases, further experimental tests for the thermohydraulic conditions of interest in advanced designs can provide improved understanding of the phenomena. Further, analytical methods to predict reactor thermohydraulic behaviour can be qualified for use by comparison with the experimental results. These activities should ultimately result in more economical designs. The

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

    International Nuclear Information System (INIS)

    1997-08-01

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

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

    International Nuclear Information System (INIS)

    1998-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

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

  16. Coaching Non-technical Skills Improves Surgical Residents' Performance in a Simulated Operating Room.

    Science.gov (United States)

    Yule, Steven; Parker, Sarah Henrickson; Wilkinson, Jill; McKinley, Aileen; MacDonald, Jamie; Neill, Adrian; McAdam, Tim

    2015-01-01

    To investigate the effect of coaching on non-technical skills and performance during laparoscopic cholecystectomy in a simulated operating room (OR). Non-technical skills (situation awareness, decision making, teamwork, and leadership) underpin technical ability and are critical to the success of operations and the safety of patients in the OR. The rate of developing assessment tools in this area has outpaced development of workable interventions to improve non-technical skills in surgical training and beyond. A randomized trial was conducted with senior surgical residents (n = 16). Participants were randomized to receive either non-technical skills coaching (intervention) or to self-reflect (control) after each of 5 simulated operations. Coaching was based on the Non-Technical Skills For Surgeons (NOTSS) behavior observation system. Surgeon-coaches trained in this method coached participants in the intervention group for 10 minutes after each simulation. Primary outcome measure was non-technical skills, assessed from video by a surgeon using the NOTSS system. Secondary outcomes were time to call for help during bleeding, operative time, and path length of laparoscopic instruments. Non-technical skills improved in the intervention group from scenario 1 to scenario 5 compared with those in the control group (p = 0.04). The intervention group was faster to call for help when faced with unstoppable bleeding in the final scenario (no. 5; p = 0.03). Coaching improved residents' non-technical skills in the simulated OR compared with those in the control group. Important next steps are to implement non-technical skills coaching in the real OR and assess effect on clinically important process measures and patient outcomes. Copyright © 2015 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  17. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  18. Electric Power Research Institute, Environmental Control Technology Center report to the steering committee. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    Operations and maintenance continued this month at the Electric Power Research Institute`s Environmental Control Technology Center. Testing on the 4.0 MW Pilot Wet FGD unit continued with the Pilot High Velocity FGD (PHV) and the Trace Element Removal (TER) test blocks. In the High Velocity test block, SO{sub 2} removal and mist eliminator carryover rates were investigated while operating the absorber unit with various spray nozzle types and vertical mist eliminator sections. During the Trace Element Removal test block, the mercury measurements and control studies involving the EPA Method 29 continued with testing of several impinger capture solutions, and the use of activated carbon injection across the Pulse-Jet Fabric Filter (PJFF) unit. The 4.0 MW Spray Dryer Absorber System was utilized this month in the TER test configuration to inject and transfer activated carbon to the PJFF bags for downstream mercury capture. Work also began in December to prepare the 0.4 MW Mini-Pilot Absorber system for receipt of the B and W Condensing Heat Exchanger (CHX) unit to be used in the 1996 DOE/PRDA testing. The 1.0 MW Cold-Side Selective Catalytic Reduction (SCR) unit remained in cold-standby this month.

  19. Nuclear power operating experience and technical improvement in Japan

    International Nuclear Information System (INIS)

    Toyota, M.

    1983-01-01

    LWR technology in Japan, originally introduced from the United States of America, is now almost entirely supplied domestically. During the initial stage of plant operation, electric power companies experienced various troubles such as intergranular stress corrosion cracking (IGSCC) in the piping in BWRs and steam generator (S/G) tube leaks in PWRs, which once reduced the capacity factor to about 40%. As a result of efforts to investigate the causes of the troubles and to establish countermeasures, which were applied to the plants in operation and under construction for improvement, as well as to shorten the period of regular inspection and to extend the operation cycle, the capacity factor has been improved to 60% since 1980. In 1975 an LWR improvement and standardization programme was launched to aim at improvement of reliability and availability factor and reduction of occupational radiation exposure with the development of domestic technology based on construction and operating experience. The First Phase Programme, which ran from 1975 to 1977, established countermeasures to preclude these troubles and improved workability by enlargement of the containment vessel. The Second Phase Programme followed and ran until 1981. The major steps taken during this period include the adoption of new IGSCC-resistant material and improved core design for BWRs and the improvement of fuels and S/Gs for PWRs. With these improvements, the capacity factor is now expected to reach a 75% level and occupational radiation exposure should be reduced by 50%. A Third Phase Programme will centre on the test and development programme for advanced BWRs and PWRs now under way to further improve the availability factor and reliability while also minimizing radiation exposure. (author)

  20. Human Performance in Continuous Operations. Volume 3. Technical Documentation

    Science.gov (United States)

    1980-03-01

    completed for the U. S. Commander, V Corps. Artillery, by Manning (1978). Manning collected information which bears on the following three questions: 0 Can...performance data were not collected in these pre- liminary studies. Field Studies of Continuous Tank OperationsLI __ _ _ __ _ _ _ To simulate a combat...on routine, monotonous tasks tends A show rapid and severe decrement after peri- odk of more than 24 hours without sleep. I Increasing task complexity

  1. The WCO/IAEA technical committee meeting to develop guidance related to illicit trafficking

    Energy Technology Data Exchange (ETDEWEB)

    Weil, L [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    1997-07-01

    Following the initiative of the Director General of the International Atomic Energy Agency, Dr. Hans Blix, of September 1995 and the subsequent resolution of the 38. session of the General Conference, the IAEA and the World Customs Organization jointly undertook action to deal with the problems that can be caused by the illicit movement of radioactive materials. The ``Illicit Trafficking Programme``, co-sponsored by the two organizations aims at developing close co-operation between the Member States` radiation and nuclear safety competent authorities and their border control and customs authority counterparts. The main elements of this programme are: (1) the development of a guidance document covering the prevention and detection of unauthorized movements of radioactive materials as well as the proper response to such activities; (2) the definition of the terms for a pilot study to test border monitoring equipment under field conditions; and (3) the creation of an IAEA/WCO training module for border control and customs officers.

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

    International Nuclear Information System (INIS)

    1997-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

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

  4. The WCO/IAEA technical committee meeting to develop guidance related to illicit trafficking

    International Nuclear Information System (INIS)

    Weil, L.

    1997-07-01

    Following the initiative of the Director General of the International Atomic Energy Agency, Dr. Hans Blix, of September 1995 and the subsequent resolution of the 38. session of the General Conference, the IAEA and the World Customs Organization jointly undertook action to deal with the problems that can be caused by the illicit movement of radioactive materials. The ''Illicit Trafficking Programme'', co-sponsored by the two organizations aims at developing close co-operation between the Member States' radiation and nuclear safety competent authorities and their border control and customs authority counterparts. The main elements of this programme are: (1) the development of a guidance document covering the prevention and detection of unauthorized movements of radioactive materials as well as the proper response to such activities; (2) the definition of the terms for a pilot study to test border monitoring equipment under field conditions; and (3) the creation of an IAEA/WCO training module for border control and customs officers

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  6. Electric Power Research Institute: Environmental Technology Control Center, report to the Steering committee. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report describes test for air pollution control of flue gas and mercury as a result of coal combustion. The NYSEG Kintigh Station provided flue gas to the Center 100% of the time during this performance period. As the Kintigh Station operated with a variety of coals, fluctuations in the Center`s inlet SO{sub 2} concentrations were experienced. Safety training for the month was conducted by the O&M Superintendent, Maintenance Supervisor and Shift Supervisors. {open_quotes}Personal Protective Equipment{close_quotes} was the topic of the month. Inspections of the ECTC Facility and safety equipment (SCR air-packs, fire extinguishers, etc.) were completed and recorded this month. All systems were found to be in good condition. By continuing to emphasize safe work habits at the Center, we have raised the total number of days without a lost time injury to 1426 as of 4/30/96. The monthly safety meeting with the NYSEG Kintigh Station was held on April 30, 1996 with both NYSEG and ECTC representatives. The topics of discussion included an overview of NYSEG`s upcoming alternate fuel burn, an update on plant staffing changes, and a discussion of future safety training activities.

  7. Special Operations Forces (SOF) technical analysis and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-08-31

    In response to Task Order 001, Los Alamos National Laboratory Contract 9-L5H-1508P-1, Betac Corporation is pleased to provide ten quick-response, short-term analytical papers in support of Low Intensity Conflict (LIC) and Special Operations (SO). The papers are study methodologies which provide background, baseline, concepts, approaches, and recommendations in the mission areas identified in the Statement of Work. Although the Statement of Work specifies only nine papers, a tenth paper has been included addressing Command Relationships, since this subject affects all other topics and is of critical importance to USCINCSOC in establishing the United States Special Operations Command (USSOCOM). Each paper addresses the feasibility of further effort in each area of interest. The ten papers address: (1) mission support systems; (2) research, development, and acquisition; (3) headquarters equipment; (4) C3I architecture; (5) intelligence dissemination; (6) intelligence collection management; (7) intelligence support to SOF targeting; (8) joint mission area analysis (JMAA); (9) joint SOF master plan; and (10) command relationships.

  8. 43 CFR 23.5 - Technical examination of prospective surface exploration and mining operations.

    Science.gov (United States)

    2010-10-01

    ... mining operations vary widely with respect to topography, climate, surrounding land uses, proximity to... surface exploration and mining operations. 23.5 Section 23.5 Public Lands: Interior Office of the Secretary of the Interior SURFACE EXPLORATION, MINING AND RECLAMATION OF LANDS § 23.5 Technical examination...

  9. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  10. Technical refolding of proteins: Do we have freedom to operate?

    Science.gov (United States)

    Eiberle, Maria K; Jungbauer, Alois

    2010-06-01

    Expression as inclusion bodies in Escherichia coli is a widely used method for the large-scale production of therapeutic proteins that do not require post-translational modifications. High expression yields and simple recovery steps of inclusion bodies from the host cells are attractive features industrially. However, the value of an inclusion body-based process is dominated by the solubilization and refolding technologies. Scale-invariant technologies that are economical and applicable for a wide range of proteins are requested by industry. The main challenge is to convert the denatured protein into its native conformation at high yields. Refolding competes with misfolding and aggregation. Thus, the yield of native monomer depends strongly on the initial protein concentrations in the refolding solution. Reasonable yields are attained at low concentrations (freedom to operate.

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

    International Nuclear Information System (INIS)

    2005-01-01

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

  12. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Bouget, Y.H.

    1994-01-01

    The seminar discussed the objectives, organization and scope of work of the Central and Site Technical Service Department in support of operating NPP; transfer of capability to establish and maintain an efficient operation support; defined the responsibilities and interface between on site and Central Technical Staff

  13. Control rod guide tube wear in operating reactors; operating experience report. Technical report December 1977-December 1979

    International Nuclear Information System (INIS)

    Riggs, R.

    1980-04-01

    Evidence of control rod guide tube wear has been observed in operating pressurized water reactors. The cause of this wear is identified as flow-induced vibration of the control rods. This report describes the measures being taken by both the industry and the NRC to deal with this matter. The staff also presents its technical positions and requirements to support continued operation of the plants as of December 1979 pending completion of this generic effort

  14. Technical evolution and operation of French CO2 cooled reactors (UNGG)

    International Nuclear Information System (INIS)

    Berthion, Y.

    1986-10-01

    The technical evolution of the five French CO 2 cooled reactors (UNGG) from 1981 to 1986 needs to be outlined. These technical evolutions concerned the fuel element of Bugey 1 which is now slightly enriched, as well as the load reduction operation required by the grid. In addition work in underway to increase the safety at the two St Laurent units, or to repair the hot steel upper-structures of Chinon-3 unit

  15. Technical challenges to energy systems' operation and markets

    Energy Technology Data Exchange (ETDEWEB)

    Soerensen, P.; Meibom, P.; Gehrke, O. [Risoe National Lab. (Denmark); Oestergaard, J. [Technical Univ. of Denmark (Denmark)

    2006-11-15

    A future energy system that includes a high proportion of renewable energy will be expected to meet the same requirements for security of supply and economic efficiency as the energy systems of today, while delivering better environmental performance, especially with regard to CO{sub 2} emissions. Security of supply refers to the long-term reliability of fuel supply; especially in power systems, it also covers short-term requirements for system stability and adequacy. Economic efficiency is concerned with getting the best from the significant amounts of money, human capital and natural resources involved in an energy system. Integral to economic efficiency in energy systems is the presence of well-functioning markets for energy services. The variability and reduced predictability of a number of renewable energy sources, notably wind power, create specific challenges for future energy systems compared to those of today. Power transmission will also become an issue, as the areas with good potential for wind power and wave energy are often located some distance from the centres of power consumption. This chapter describes the challenges involved, and possible solutions to these, with a focus on power systems. The chapter is divided into two sections reflecting the fact that some challenges relate to managing the power system in its normal operation mode, whereas others are specific to fault conditions. (au)

  16. Non-technical skills of surgeons and anaesthetists in simulated operating theatre crises.

    Science.gov (United States)

    Doumouras, A G; Hamidi, M; Lung, K; Tarola, C L; Tsao, M W; Scott, J W; Smink, D S; Yule, S

    2017-07-01

    Deficiencies in non-technical skills (NTS) have been increasingly implicated in avoidable operating theatre errors. Accordingly, this study sought to characterize the impact of surgeon and anaesthetist non-technical skills on time to crisis resolution in a simulated operating theatre. Non-technical skills were assessed during 26 simulated crises (haemorrhage and airway emergency) performed by surgical teams. Teams consisted of surgeons, anaesthetists and nurses. Behaviour was assessed by four trained raters using the Non-Technical Skills for Surgeons (NOTSS) and Anaesthetists' Non-Technical Skills (ANTS) rating scales before and during the crisis phase of each scenario. The primary endpoint was time to crisis resolution; secondary endpoints included NTS scores before and during the crisis. A cross-classified linear mixed-effects model was used for the final analysis. Thirteen different surgical teams were assessed. Higher NTS ratings resulted in significantly faster crisis resolution. For anaesthetists, every 1-point increase in ANTS score was associated with a decrease of 53·50 (95 per cent c.i. 31·13 to 75·87) s in time to crisis resolution (P technical skills scores were lower during the crisis phase of the scenarios than those measured before the crisis for both surgeons and anaesthetists. A higher level of NTS of surgeons and anaesthetists led to quicker crisis resolution in a simulated operating theatre environment. © 2017 BJS Society Ltd Published by John Wiley & Sons Ltd.

  17. Assessing Nurse Anaesthetists' Non-Technical Skills in the operating room.

    Science.gov (United States)

    Lyk-Jensen, H T; Jepsen, R M H G; Spanager, L; Dieckmann, P; Østergaard, D

    2014-08-01

    Incident reporting and fieldwork in operating rooms have shown that some of the errors that arise in anaesthesia relate to inadequate use of non-technical skills. To provide a tool for training and feedback on nurse anaesthetists' non-technical skills, this study aimed to adapt the Anaesthetists' Non-Technical Skills (ANTS) as a behavioural marker system for the formative assessment of nurse anaesthetists' non-technical skills in the operating room. A qualitative approach with focus group interviews was used to identify the non-technical skills of nurse anaesthetists in the operating room. The interview data were transcribed verbatim. Directed content analysis was used to code and sort data deductively into the ANTS categories: task management, team working, situation awareness and decision making. The prototype named Nurse Anaesthetists' Non-Technical Skills (N-ANTS) was presented and discussed in a group of subject matter experts to ensure face validity. The N-ANTS system consists of the same four categories as ANTS and 15 underlying elements. Three to five good and poor behavioural markers for each element were identified. The headings and definitions of the categories and elements were adjusted to encompass the behavioural markers in N-ANTS. The differences that emerged mainly reflected statements regarding the establishment of role, competence, and task delegation. A behavioural marker system, N-ANTS, for nurse anaesthetists was adapted from a behavioural marker system, ANTS, for anaesthesiologists. © 2014 The Acta Anaesthesiologica Scandinavica Foundation. Published by John Wiley & Sons Ltd.

  18. Additive Manufacturing (AM) in Expeditionary Operations: Current Needs, Technical Challenges, and Opportunities

    Science.gov (United States)

    2016-06-01

    REPORT TYPE AND DATES COVERED Master’s Thesis 06-30-2014 to 06-17-2016 4. TITLE AND SUBTITLE ADDITIVE MANUFACTURING (AM) IN EXPEDITIONARY OPERATIONS: CUR...CODE 13. ABSTRACT (maximum 200 words) Additive manufacturing (AM), or 3D printing, is poised to change the world of military expeditionary operations...unlimited ADDITIVE MANUFACTURING (AM) IN EXPEDITIONARY OPERATIONS: CURRENT NEEDS, TECHNICAL CHALLENGES, AND OPPORTUNITIES Matthew Daniel Friedell Captain

  19. Scientific, Technical and Economic Committee for Fisheries (STECF) – Opinion by written procedure – Review of scientific advice for 2013- part I – Advice on stocks in the Baltic Sea

    DEFF Research Database (Denmark)

    The scientific advice on the stocks and fisheries in the Baltic Sea in 2013 evaluated and endorsed by the Scientific, Technical and Economic Committee for Fisheries (STECF) by written procedure in June 2012 on a request by the European Commission......The scientific advice on the stocks and fisheries in the Baltic Sea in 2013 evaluated and endorsed by the Scientific, Technical and Economic Committee for Fisheries (STECF) by written procedure in June 2012 on a request by the European Commission...

  20. Operating environment threats influence on the maritime ferry technical system safety – the numerical approach

    Directory of Open Access Journals (Sweden)

    Kuligowska Ewa

    2017-06-01

    Full Text Available The material given in this paper delivers the procedure for numerical approach that allows finding the main practically important safety characteristics of the complex technical systems at the variable operation conditions including operating environment threats. The obtained results are applied to the safety evaluation of the maritime ferry technical system. It is assumed that the conditional safety functions are different at various operation states and have the exponential forms. Using the procedure and the program written in Mathematica, the considered maritime ferry technical system main characteristics including: the conditional and the unconditional expected values and standard deviations of the system lifetimes, the unconditional safety function and the risk function are determined.

  1. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Groom, S.H.

    1994-01-01

    The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

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

    International Nuclear Information System (INIS)

    2015-01-01

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

  3. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

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

    International Nuclear Information System (INIS)

    2002-01-01

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

  5. ASTM Committee C28: International Standards for Properties and Performance of Advanced Ceramics-Three Decades of High-Quality, Technically-Rigorous Normalization

    Science.gov (United States)

    Jenkins, Michael G.; Salem, Jonathan A.

    2016-01-01

    Physical and mechanical properties and performance of advanced ceramics and glasses are difficult to measure correctly without the proper techniques. For over three decades, ASTM Committee C28 on Advanced Ceramics, has developed high-quality, technically-rigorous, full-consensus standards (e.g., test methods, practices, guides, terminology) to measure properties and performance of monolithic and composite ceramics that may be applied to glasses in some cases. These standards contain testing particulars for many mechanical, physical, thermal, properties and performance of these materials. As a result these standards are used to generate accurate, reliable, repeatable and complete data. Within Committee C28, users, producers, researchers, designers, academicians, etc. have written, continually updated, and validated through round-robin test programs, 50 standards since the Committee's founding in 1986. This paper provides a detailed retrospective of the 30 years of ASTM Committee C28 including a graphical pictogram listing of C28 standards along with examples of the tangible benefits of standards for advanced ceramics to demonstrate their practical applications.

  6. Radioactive Operations Committee Review of the Intermediate-Level Waste Evaporator Facility, Building 2531 February 17, 1972

    International Nuclear Information System (INIS)

    Liberman, B.; Brooksbank, R.E.

    1972-01-01

    A subcommittee of the Radioactive Operations Committee met with the Operators of the Intermediate Level Waste Evaporator Facility on February 17, 1972, to discuss the status of the facility and its operations since the review of October 7, 1970, and reported in ORNL-CF-70-11-12. This review was made to determine the status of the ILWEF since the last review, to discuss compliance with previously recommended changes, and to review any new items of safety significance. Several recommendations were made.

  7. 78 FR 11671 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2013-02-19

    ... Term. 5. Discuss the Statement of Work and Next Steps regarding the Global Supply Chain Subcommittee... and Border Protection, Department of Homeland Security (DHS). ACTION: Committee Management; Notice of...

  8. Technical co-operation report for 2002. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    General Conference resolution GC(46)/RES/10 reiterated the need to strengthen the technical co- operation programme and requested the Director General to report to the Board of Governors periodically and to the General Conference at its forty-seventh (2003) session on the implementation of resolution GC(46)/RES/10. Part A of this report responds to the General Conference resolution by providing an overview of the progress achieved in technical co-operation policies, strategies, working relations, and internal management during the period 1 April 2002 to 31 March 2003, as well as the major new challenges facing the technical co-operation programme. Part B reports on operational activities and programme performance at the country and regional levels during the calendar year 2002, and Part C reviews the use of financial and human resources in the programme at an aggregate level. As part of its efforts to refine policies for improving programme development, the Agency reviewed the Technical Co-operation Strategy in 2002. The resulting document, The Technical Co-operation Strategy: the 2002 Review (document GOV/INF/2002/8/Mod.1), states that the strategic goal originally identified in the Strategy in 1997 remains valid, and defines four objectives to guide the technical co-operation programme: applying the central criterion (strong government commitment), developing strategic partnerships, increasing the level of funding for technical co-operation, and promoting greater sustainability and self-reliance of nuclear institutions. In line with the Technical Co-operation Strategy, one of the key features of the Agency.s work in 2002 was continuing consultations with Member States at both the policy and operational levels on the management of the ongoing technical co-operation programme and on planning for future activities. The dialogue with Member States aimed at clarifying the strategic objectives and key tools for the utilization of resources to achieve maximum

  9. Non-technical skills of the operating theatre scrub nurse: literature review.

    Science.gov (United States)

    Mitchell, Lucy; Flin, Rhona

    2008-07-01

    This paper is a report of a review to identify the non-technical (cognitive and social) skills used by scrub nurses. Recognition that failures in non-technical skills contributed to accidents in high-risk industries led to the development of research programmes to study the role of cognition and social interactions in operational safety. Recently, psychological research in operating theatres has revealed the importance of non-technical skills in safe and efficient performance. Most of the studies to date have focused on anaesthetists and surgeons. On-line sources and university library catalogues, publications of the Association for Perioperative Practice, National Association of Theatre Nurses and Association of Peri-Operative Registered Nurses were searched in 2007. Studies were included in the review if they presented data from scrub nurses on one or more of their non-technical skills. These findings were examined in relation to an existing medical non-technical skills framework with categories of communication, teamwork, leadership, situation awareness and decision-making. Of 424 publications retrieved, 13 were reviewed in detail. Ten concerned communication and eight of those also had data on teamwork. In 11 papers teamwork was examined, and one focused on nurses' situation awareness, teamwork and communication. None of the papers we reviewed examined leadership or decision-making by scrub nurses. Further work is needed to identify formally the non-technical skills which are important to the role of scrub nurse and then to design training in the identified non-technical skills during the education and development of scrub nurses.

  10. Report on operation utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1982-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1980 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  11. Report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1980-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1978 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  12. Tore Supra: technical aspects and early results after one year of operation

    International Nuclear Information System (INIS)

    Gravier, R.

    1989-01-01

    After one year operation (1988 to 1989), technical aspects of component systems and equipment of Tore Supra are summarized. Particular attention is given to the operation with: supraconducting toroidal field coil system, cryogenic system, poloidal field system, in vessel equipment, first wall conditioning, pump limiter. The ergodic divertor experiments and the current drive experiment are reported. The plasma heating methods adopted in Tore Supra are presented

  13. Report on operation, utilization and technical development of Research Reactors and Hot Laboratory

    International Nuclear Information System (INIS)

    1984-10-01

    Activities of the Division of Research Reactor Operation in fiscal 1981 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  14. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  15. Technical Diagnostics of Ventilation Units for Energy Efficiency and Safety of Operation

    Directory of Open Access Journals (Sweden)

    Kuzin Evgeny

    2017-01-01

    Full Text Available The article considers the questions of application of technical diagnostics fan installations methods for providing safe operation, the system of the technical maintenance improvement and repair. Due to the feet that one of the most important aspects in fan operation in mining is energy efficiency and energy saving, the lack of the data in the control of the level in vibration of stationary sensors is shown. The necessity of taking into account the geometric parameters of the intake channel has been shown, and also the necessity of creation of the reference masks for the assessment of technical condition and energy efficiency when operating fan installations in mining. The results of technical diagnostics of the main fans using the methods of vibration diagnostics are provided. Aspects of vibration at characteristic points are shown. The necessity for further accumulation of data characterizing vibration for adjustment of the reference masks and more accurate detection of defects and deviations from the energy-efficient mode of operation of the fan installations is given.

  16. The IAEA technical Co-operation a partner in development in Latin America

    Energy Technology Data Exchange (ETDEWEB)

    El-Saiedi, A [International Atomic Energy Agency, Vienna (Austria). Div. of Public Information

    1995-10-01

    Each country was to find means of achieving sustainable development, and for this, technology within a framework of regional and international co-operation are of utmost importance. The IAEA plays a major role in promoting nuclear technologies for development. Highlights of the IAEA`s technical cooperation programme are given in this paper.

  17. The IAEA technical Co-operation a partner in development in Latin America

    International Nuclear Information System (INIS)

    El-Saiedi, A.

    1995-01-01

    Each country was to find means of achieving sustainable development, and for this, technology within a framework of regional and international co-operation are of utmost importance. The IAEA plays a major role in promoting nuclear technologies for development. Highlights of the IAEA's technical cooperation programme are given in this paper

  18. Technical Diagnostics of Ventilation Units for Energy Efficiency and Safety of Operation

    Science.gov (United States)

    Kuzin, Evgeny; Shahmanov, Vitality; Dubinkin, Dmitriy

    2017-11-01

    The article considers the questions of application of technical diagnostics fan installations methods for providing safe operation, the system of the technical maintenance improvement and repair. Due to the feet that one of the most important aspects in fan operation in mining is energy efficiency and energy saving, the lack of the data in the control of the level in vibration of stationary sensors is shown. The necessity of taking into account the geometric parameters of the intake channel has been shown, and also the necessity of creation of the reference masks for the assessment of technical condition and energy efficiency when operating fan installations in mining. The results of technical diagnostics of the main fans using the methods of vibration diagnostics are provided. Aspects of vibration at characteristic points are shown. The necessity for further accumulation of data characterizing vibration for adjustment of the reference masks and more accurate detection of defects and deviations from the energy-efficient mode of operation of the fan installations is given.

  19. Technical co-operation report for 2002. Report by the Director General

    International Nuclear Information System (INIS)

    2003-08-01

    General Conference resolution GC(46)/RES/10 reiterated the need to strengthen the technical co- operation programme and requested the Director General to report to the Board of Governors periodically and to the General Conference at its forty-seventh (2003) session on the implementation of resolution GC(46)/RES/10. Part A of this report responds to the General Conference resolution by providing an overview of the progress achieved in technical co-operation policies, strategies, working relations, and internal management during the period 1 April 2002 to 31 March 2003, as well as the major new challenges facing the technical co-operation programme. Part B reports on operational activities and programme performance at the country and regional levels during the calendar year 2002, and Part C reviews the use of financial and human resources in the programme at an aggregate level. As part of its efforts to refine policies for improving programme development, the Agency reviewed the Technical Co-operation Strategy in 2002. The resulting document, The Technical Co-operation Strategy: the 2002 Review (document GOV/INF/2002/8/Mod.1), states that the strategic goal originally identified in the Strategy in 1997 remains valid, and defines four objectives to guide the technical co-operation programme: applying the central criterion (strong government commitment), developing strategic partnerships, increasing the level of funding for technical co-operation, and promoting greater sustainability and self-reliance of nuclear institutions. In line with the Technical Co-operation Strategy, one of the key features of the Agency.s work in 2002 was continuing consultations with Member States at both the policy and operational levels on the management of the ongoing technical co-operation programme and on planning for future activities. The dialogue with Member States aimed at clarifying the strategic objectives and key tools for the utilization of resources to achieve maximum

  20. Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 December 2002

    International Nuclear Information System (INIS)

    2002-11-01

    The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing their consequences. The International Atomic Energy Agency (IAEA) has specific functions assigned to it under these Conventions, to which, in addition to a large number of States (Section 1.7), the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. The arrangements between the IAEA, States that are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of these Conventions specifically concerning those articles that are operational in nature - are documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). In 2000, a complete revision of ENATOM, with all relevant sections updated, withdrawn or replaced with new material, was reissued as EPR-ENATOM (2000) to reflect new technological developments, operational concepts, views on standards in the area of emergency preparedness and response, and Member States' expectations. A separate publication, EPR-JPLAN (2000), the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan'), described a common understanding of how each of six co-sponsoring international organizations will act during a response and in making preparedness arrangements. It is intended that the ENATOM is reviewed and reissued biennially in line with the review cycle of the Joint Plan. Since the

  1. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-08-01

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

  3. 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)

  4. Report on International Spaceborne Imaging Spectroscopy Technical Committee Calibration and Validation Workshop, National Environment Research Council Field Spectroscopy Facility, University of Edinburgh

    Science.gov (United States)

    Ong, C,; Mueller, A.; Thome, K.; Bachmann, M.; Czapla-Myers, J.; Holzwarth, S.; Khalsa, S. J.; Maclellan, C.; Malthus, T.; Nightingale, J.; hide

    2016-01-01

    Calibration and validation are fundamental for obtaining quantitative information from Earth Observation (EO) sensor data. Recognising this and the impending launch of at least five sensors in the next five years, the International Spaceborne Imaging Spectroscopy Technical Committee instigated a calibration and validation initiative. A workshop was conducted recently as part of this initiative with the objective of establishing a good practice framework for radiometric and spectral calibration and validation in support of spaceborne imaging spectroscopy missions. This paper presents the outcomes and recommendations for future work arising from the workshop.

  5. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  6. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  7. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  8. On the issue of selecting technical and operational parameters for buses in urban passenger routes

    Directory of Open Access Journals (Sweden)

    Rudzinskyi V.V.

    2017-10-01

    Full Text Available Problems of a public transport bus service in urban areas were analyzed. The aim of the article is to determine actual operational parameters of buses during passenger transportation in Zhytomyr. Ways of determining technical and operational parameters of buses were developed using visual and tabular methods of city buses real-time speed and acceleration performance registration by GPS-monitoring system with the help of a communicational and informational intelligent transport system of the city. Experimental studies of city buses motion parameters were presented. A comprehensive survey of passenger traffic and conditions of public transport functioning in Zhytomyr was carried out. The values of technical and operational parameters of buses on city routes were obtained. Preliminarily conclusions and recommendations considering the criteria for selecting the optimal rolling stock for a bus network of the city were suggested.

  9. Technical co-operation report for 1998. Report by the Director General

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries

  10. Technical co-operation report for 1998. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents the IAEA Technical Co-operation (TC) activities during 1998 and highlights most significant accomplishments. Part I of this report reviews the strengthening of TC, both in financial aspects and through implementation of the TC strategy. Part II reviews extensively the actual output of the TC programme; it looks at each geographic region, and reports on the results of national, regional and, where applicable, interregional activities in those regions. Part III presents a technical discussion of the financial parameters of the TC programme and ends with financial implementation summaries.

  11. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  12. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Technical session: Operation and safety of nuclear installations, fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Bereich Reaktorsicherheitsforschung

    2017-12-15

    The sessions Fuel and Materials and Containment and SFP, as part of the Technical Sessions Operation and Safety of Nuclear Installations, Fuel implemented in the Key Topic Enhanced Safety and Operation Excellence were chaired by Dr. Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) and Dr. Erwin Fischer (PreussenElektra GmbH) who was the keynote coordinator for the Technical Sessions. Both sessions consist of a keynote lecture followed by technical presentations.

  13. IEEE Committee on Man and Radiation--COMAR technical information statement radiofrequency safety and utility Smart Meters.

    Science.gov (United States)

    Bushberg, Jerrold T; Foster, Kenneth R; Hatfield, James B; Thansandote, Arthur; Tell, Richard A

    2015-03-01

    This Technical Information Statement describes Smart Meter technology as used with modern electric power metering systems and focuses on the radio frequency (RF) emissions associated with their operation relative to human RF exposure limits. Smart Meters typically employ low power (-1 W or less) transmitters that wirelessly send electric energy usage data to the utility company several times per day in the form of brief, pulsed emissions in the unlicensed frequency bands of 902-928 MHz and 2.4-2.48 GHz or on other nearby frequencies. Most Smart Meters operate as wireless mesh networks where each Smart Meter can communicate with other neighboring meters to relay data to a data collection point in the region. This communication process includes RF emissions from Smart Meters representing energy usage as well as the relaying of data from other meters and emissions associated with maintaining the meter's hierarchy within the wireless network. As a consequence, most Smart Meters emit RF pulses throughout the day, more at certain times and less at others. However, the duty cycle associated with all of these emissions is very small, typically less than 1%, and most of the time far less than 1%, meaning that most Smart Meters actually transmit RF fields for only a few minutes per day at most. The low peak power of Smart Meters and the very low duty cycles lead to the fact that accessible RF fields near Smart Meters are far below both U.S. and international RF safety limits whether judged on the basis of instantaneous peak power densities or time-averaged exposures. This conclusion holds for Smart Meters alone or installed in large banks of meters.

  14. 77 FR 26564 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2012-05-04

    ... National Strategy for Global Supply Chain Security. The work of the Trade Facilitation Subcommittee... Strategy for Global Supply Chain Security as it relates to the Committee's effort to solicit, consolidate... chain management project. The Anti-Dumping/Countervailing Duties Subcommittee work on educational...

  15. 77 FR 68802 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2012-11-16

    ... Strategy for Global Supply Chain Security as it relates to an effort to solicit, consolidate, and provide... of entry to help identify counterfeit products, the distribution chain management and serialization... and Border Protection, Department of Homeland Security (DHS). ACTION: Committee Management; Notice of...

  16. 78 FR 64968 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2013-10-30

    ... regarding the Partner Government Agency--Message Set (PGA-MS). 2. The Global Supply Chain Subcommittee... the Global Shipment Identification Number (GSIN) as a possible tool for use in Distribution Chain... and Border Protection, Department of Homeland Security (DHS). ACTION: Committee Management; Notice of...

  17. 78 FR 43220 - Advisory Committee on Commercial Operations of Customs and Border Protection (COAC)

    Science.gov (United States)

    2013-07-19

    ... Standards Working Group (ISWG) and the Trusted Trader Measures Working Group. 6. The Global Supply Chain... Distribution Chain Management in Intellectual Property Rights Compliance. 4. The One U.S. Government at the... and Border Protection, Department of Homeland Security (DHS). ACTION: Committee Management; Notice of...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

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

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

    International Nuclear Information System (INIS)

    2002-04-01

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

  20. Technical Co-operation Report for 1996. Report by the Director General

    International Nuclear Information System (INIS)

    1997-01-01

    The Agency's Technical Cooperation (TC) Programme made further progress during 1996 in implementing recent initiatives to strengthen efficiency and effectiveness. These initiatives seek to maximize the developmental contribution of counterpart institutions by emphasizing the management of technology to solve social and economic problems. The new direction has been embodied in the term ''Partners in Development''. The Partners in Development approach is reflected in last year's Report to the Board of Governors and the General Conference on Strengthening of the Agency's Technical Co-operation Activities, which provided an update on ongoing activities and elaborated new initiatives. The 1995 Technical Cooperation Report focused on the progress in implementing these initiatives. Next year, the Secretariat plans to combine the TC Report with the Report on Strengthening of the Agency's Technical Co-operation Activities in order to improve the clarity, consistency and economy of these presentations. Establishing a development partnership with Member States is the central goal of a new Strategy for TC. The refinement of this strategy required considerable effort during 1996, when the process first began to define objectives, targets and the means of accomplishing them. Alongside internal consultations, the role of SAGTAC became instrumental in reaching consensus on the main elements of the strategy. Future efforts include the formulation of implementation plans for the strategy. Once completed, the strategy will be presented to the TACC and Board in 1997. Reflecting these developments, section A of this Report presents the basic features of the TC Strategy, and the approach to be taken to achieve its objectives. The Strategy addresses among others the recommendations contained in resolution GC(40)/RES/13 on the Strengthening of Technical Co-operation: activities to improve the scientific and technological capabilities of developing countries; to achieve sustainable

  1. An ethics for the living world: operation methods of Animal Ethics Committees in Italy

    Directory of Open Access Journals (Sweden)

    Mariano Martini

    2015-09-01

    Full Text Available INTRODUCTION AND OBJECTIVES. Coinciding with the recent implementation in Italy of the "Directive 2010/63/EU, regarding the protection of animals used for scientific purposes", the Authors would like to analyse the topic of the introduction of ethical committees for animal experimentation in Italy. This paper furthermore aims to underline some critical aspects concerning the actions taken by Italian institutions to comply with the provisions of EU. RESULTS AND DISCUSSION. The implementation of the recent Italian law (Decreto Legislativo n. 26 on 4 March 2014 Implementation of the Directive 2010/63/EU on the protection of animals used for scientific purposes leans towards a restrictive interpretation of the European provisions about composition and responsibilities of "Ethical Committee for Animal Experimentation". In the composition of the bodies mentioned, we note a tendency to restrict the composition to few professional figures contemplated by Italian law, without guaranteeing the independence of each committee; also, an absence of hierarchical relationship between a research institution and his committee is apparent. Moreover, a critical aspect is the lack of decision-making powers of these new organisms in terms of ethical evaluation of protocols and research projects. CONCLUSIONS. What EU legislation imposes on the member states is to set up an animal-welfare body (art. 26. This represents a strong incentive for Italy to follow the steps of many other European Countries, where ad hoc ethical committees have been working for a long time. The proper functioning of these bodies may contribute to guarantee the safety and welfare of the animals inside the laboratories, and to balance the protection of animal life and the interests of research.

  2. Ten years's reactor operation at the Technical University Zittau - operation report

    International Nuclear Information System (INIS)

    Konschak, K.

    1990-01-01

    The Zittau Training and Research Reactor ZLFR is in use for purposes of teaching the engineers who will operate the nuclear power plants in the GDR since 10 years. Since commissioning it was started up more than 1600 times, approximately two thirds of the start-ups being utilized for purposes of teaching. A number of teaching experiments were installed that demonstrate fundamental technological processes in nuclear reactors in a manner easy to understand. The high level of nuclear safety manifests itself, among other things, in extremely low radiation exposures of the operating personal and the persons to be trained. (author)

  3. Liability for damage caused by ground subsidence in the Netherlands. The role of the Mining Law and the Technical Committee Ground Subsidence

    International Nuclear Information System (INIS)

    Roggenkamp, M.M.; Verwer, Ch.P.

    2004-01-01

    This article provides an overview of the legal regulatory framework in respect of movements of the soil (i.e. subsidence and earth tremors) following the exploration and extraction of minerals in the Netherlands, and the liability for the damage they cause. This legal framework has been changed considerably since the new Mining Act came into force on January 1st, 2003. After having examined the causes of subsidence and subsequent earth tremors, and relationships with the exploration and extraction of subsoil minerals such as oil, gas, salt and coal, the article continues by presenting the legislation of this area. The authors analyse the applicable legislation before as well as after the introduction of the new Mining Act. The two judicial regimen have a similar approach: While the rules and regulations concerning earth movements are laid down in the Mining Act, the legal foundation for the liability for damage resulting from earth movements is provided by the Civil Code. The parliamentary debates on the Mining Bill specifically dealt with the issue of earth movements and the question whether either a system of absolute (vicarious) liability would apply, or a system of strict liability. One of the reasons for not having a system of absolute liability was the wish of Parliament to lay down in the Mining Act provisions for the creation of a Technical Committee on Earth Movements. It is the remit of this Committee to advise the Minister of Economic Affairs on all matters related to movements of the soil. It's duty is also to advise on the causal) relationship between mining activities and earth movements, and the amount of damages to be paid by the mining companies, at the request of individual persons. In order to avoid individuals not receiving any compensation for damages, the new Mining Act also calls for the introduction of a special Fund for Mining Damages. Individual persons would be entitled to make a claim to this fund in situations such as the mining company

  4. Technical co-operation report for 2001. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

  5. Technical co-operation report for 2001. Report by the Director General

    International Nuclear Information System (INIS)

    2001-01-01

    Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

  6. Technical Condition of Earthen Dams at Nizhegorodskaya HPP After 60 Years of Operation

    Energy Technology Data Exchange (ETDEWEB)

    Kuznetsov, V. S., E-mail: kuznetsovVS@vniig.ru; Ladenko, S. Yu., E-mail: ladenko@yandex.ru [B. E. Vedeneev All-Russian Research Institute of Hydraulic Engineering (JSC) (Russian Federation)

    2016-03-15

    The complex of hydraulic engineering installations includes five earthen dams. All facilities are of Class I. The diagnostic parameters of dam operation and technical condition monitored via in-situ observation for seepage mode, seepage strength, settlement, static stability, etc. generally meet design assumptions and safety criteria. Despite individual defects and signs of “aging” identified over the period of earthen dam operation, these are currently in a satisfactory and operable state. The long, 60-year operating period of the dams with no serious overhauls or emergencies has demonstrated the high reliability of the facilities, the correctness of the design and technological solutions adopted and implemented in the construction, and the high professional level of their operation in close cooperation with science.

  7. Annual report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1990-09-01

    This report describes the activities of the Department of Research Reactor Operation in fiscal year of 1989. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 was reconstructed to enhance the performance for utilization. The first criticality was achieved on March 22, 1989, and it subsequently went into operation. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

  8. Technical and operational organisation of the 'Swiss Marketplace': GridCode CH

    International Nuclear Information System (INIS)

    Imhof, K.; Baumann, R.

    2001-01-01

    This article describes the minimum requirements placed on the operators of electricity grids by the planned Swiss Electricity Market Law. These are compiled in the Swiss Grid Code - GridCode CH. The various players in an open electricity market such as generating companies, power brokers, those responsible for balance groups, grid operators, system co-ordinators, the operators of fine distribution networks and the final consumer and the roles they play are examined. The history of the development of the Grid Code, which contains technical and operational regulations for the successful co-operation of the market players, is reviewed. The contractual obligations of the partners involved and, in particular, regulations concerning metering, measured value designation and the provision of data are discussed

  9. Technical co-operation report for 1999. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-01

    This report presents the IAEA Technical Co-operation (TC) activities in 1999 and covers three separate topics. Part I reports on the Strengthening of TC and looks at the elements of the TC Strategy and how they contributed to the TC Programme. Part II reports on the major achievements of the TC Programme in 1999 in different regions of the world. In addition to reviewing some of the results of national and regional activities in each region - including activities under Regional Co-operation Agreements - this section looks at three interregional projects, and provides highlights of selected projects that were closed in 1999. Part III presents a technical discussion of the financial parameters of the TC Programme. A more detailed review of resources and contributions, disbursements, and non-financial indicators is provided in a Supplement to this report.

  10. Technical co-operation report for 1999. Report by the Director General

    International Nuclear Information System (INIS)

    2000-08-01

    This report presents the IAEA Technical Co-operation (TC) activities in 1999 and covers three separate topics. Part I reports on the Strengthening of TC and looks at the elements of the TC Strategy and how they contributed to the TC Programme. Part II reports on the major achievements of the TC Programme in 1999 in different regions of the world. In addition to reviewing some of the results of national and regional activities in each region - including activities under Regional Co-operation Agreements - this section looks at three interregional projects, and provides highlights of selected projects that were closed in 1999. Part III presents a technical discussion of the financial parameters of the TC Programme. A more detailed review of resources and contributions, disbursements, and non-financial indicators is provided in a Supplement to this report

  11. EVALUATING THE OVERALL TECHNICAL EFFICIENCY OF ISLAMIC BANKS OPERATING IN THE MENA REGION DURING THE FINANCIAL CRISIS.

    Directory of Open Access Journals (Sweden)

    Ali Said

    2013-04-01

    Full Text Available The present paper measured overall technical efficiency of Islamic banks operating in the MENA region during the financial crisis of 2007-2009 to address the question what are the levels of overall, pure technical and scale efficiency of Islamic banks operating in the MENA region and how they evolved during the financial crisis. This paper addresses this question technical, pure technical, and scale efficiency measures are analyzed by employing on-parametric technique, Data Envelopment Analysis (DEA. The study results suggested that Islamic banks in other MENA countries and North Africa on an average are relatively technically inefficient. This might be due to the underdeveloped banking system in those countries. In addition, the decomposition of technical efficiency into pure technical and scale efficiency shows that on average, the Islamic banks in North Africa counties and other MENA counties are having problems in the allocation of resources between their inputs and outputs mix compare to Islamic banks in GCC.

  12. MATHEMATICAL MODELS OF PROCESSES AND SYSTEMS OF TECHNICAL OPERATION FOR ONBOARD COMPLEXES AND FUNCTIONAL SYSTEMS OF AVIONICS

    Directory of Open Access Journals (Sweden)

    Sergey Viktorovich Kuznetsov

    2017-01-01

    Full Text Available Modern aircraft are equipped with complicated systems and complexes of avionics. Aircraft and its avionics tech- nical operation process is observed as a process with changing of operation states. Mathematical models of avionics pro- cesses and systems of technical operation are represented as Markov chains, Markov and semi-Markov processes. The pur- pose is to develop the graph-models of avionics technical operation processes, describing their work in flight, as well as during maintenance on the ground in the various systems of technical operation. The graph-models of processes and sys- tems of on-board complexes and functional avionics systems in flight are proposed. They are based on the state tables. The models are specified for the various technical operation systems: the system with control of the reliability level, the system with parameters control and the system with resource control. The events, which cause the avionics complexes and func- tional systems change their technical state, are failures and faults of built-in test equipment. Avionics system of technical operation with reliability level control is applicable for objects with constant or slowly varying in time failure rate. Avion- ics system of technical operation with resource control is mainly used for objects with increasing over time failure rate. Avionics system of technical operation with parameters control is used for objects with increasing over time failure rate and with generalized parameters, which can provide forecasting and assign the borders of before-fail technical states. The pro- posed formal graphical approach avionics complexes and systems models designing is the basis for models and complex systems and facilities construction, both for a single aircraft and for an airline aircraft fleet, or even for the entire aircraft fleet of some specific type. The ultimate graph-models for avionics in various systems of technical operation permit the beginning of

  13. Resolution of digital instrumentation and control and human factors technical and regulatory issues for new plants and for modernization of operating plants

    International Nuclear Information System (INIS)

    Naser, J.A.; Torok, R.C.; Canavan, K.T.

    2008-01-01

    There are several technical and regulatory issues in the areas of digital I and C, human factors, and control rooms needing generic resolution. If they are not generically resolved, they can contribute to protracted regulatory reviews for operating plant license amendments and substantial delays and increased costs for new plant COL approvals. Therefore; a coordinated, proactive program has been established to resolve key issues. Both Industry and NRC have roles in resolving these key issues and addressing them in future design efforts and regulatory reviews. The Industry initiative is led by the NEI Digital I and C and Human Factors Working Group. NRC has established Task Working Groups under the NRC Digital I and C Steering Committee to address the issues and interact with Industry. EPRI is providing technical input and resolution leadership for some of the issues being addressed in three of the task working groups. For the Highly Integrated Control Room - Human Factors Task area, EPRI has taken the lead in developing draft industry position technical reports for the following three issues: 1) Minimum inventory of human system interfaces, 2) Computerized procedures and associated topics of automation and soft controls, and 3) Methodology to determine the acceptability of manual operator actions response times for a BTP 7-19 software common cause failure. For the Diversity and Defense-in-Depth area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Integrating defensive measures and diversity attributes to protect against digital common cause failures and 2) Susceptibility of digital devices and components to common cause failures. For the Risk Informing area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Clarifying how to use current methods to model digital systems in a PRA and 2) Application of PRA to specific digital I and C issues

  14. Regular pipeline maintenance of gas pipeline using technical operational diagnostics methods

    Energy Technology Data Exchange (ETDEWEB)

    Volentic, J [Gas Transportation Department, Slovensky plynarensky priemysel, Slovak Gas Industry, Bratislava (Slovakia)

    1998-12-31

    Slovensky plynarensky priemysel (SPP) has operated 17 487 km of gas pipelines in 1995. The length of the long-line pipelines reached 5 191 km, distribution network was 12 296 km. The international transit system of long-line gas pipelines ranged 1 939 km of pipelines of various dimensions. The described scale of transport and distribution system represents a multibillion investments stored in the ground, which are exposed to the environmental influences and to pipeline operational stresses. In spite of all technical and maintenance arrangements, which have to be performed upon operating gas pipelines, the gradual ageing takes place anyway, expressed in degradation process both in steel tube, as well as in the anti-corrosion coating. Within a certain time horizon, a consistent and regular application of methods and means of in-service technical diagnostics and rehabilitation of existing pipeline systems make it possible to save substantial investment funds, postponing the need in funds for a complex or partial reconstruction or a new construction of a specific gas section. The purpose of this presentation is to report on the implementation of the programme of in-service technical diagnostics of gas pipelines within the framework of regular maintenance of SPP s.p. Bratislava high pressure gas pipelines. (orig.) 6 refs.

  15. Regular pipeline maintenance of gas pipeline using technical operational diagnostics methods

    Energy Technology Data Exchange (ETDEWEB)

    Volentic, J. [Gas Transportation Department, Slovensky plynarensky priemysel, Slovak Gas Industry, Bratislava (Slovakia)

    1997-12-31

    Slovensky plynarensky priemysel (SPP) has operated 17 487 km of gas pipelines in 1995. The length of the long-line pipelines reached 5 191 km, distribution network was 12 296 km. The international transit system of long-line gas pipelines ranged 1 939 km of pipelines of various dimensions. The described scale of transport and distribution system represents a multibillion investments stored in the ground, which are exposed to the environmental influences and to pipeline operational stresses. In spite of all technical and maintenance arrangements, which have to be performed upon operating gas pipelines, the gradual ageing takes place anyway, expressed in degradation process both in steel tube, as well as in the anti-corrosion coating. Within a certain time horizon, a consistent and regular application of methods and means of in-service technical diagnostics and rehabilitation of existing pipeline systems make it possible to save substantial investment funds, postponing the need in funds for a complex or partial reconstruction or a new construction of a specific gas section. The purpose of this presentation is to report on the implementation of the programme of in-service technical diagnostics of gas pipelines within the framework of regular maintenance of SPP s.p. Bratislava high pressure gas pipelines. (orig.) 6 refs.

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1996-01-01

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

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  2. Use of experience for the improvement of technical specifications for operation

    International Nuclear Information System (INIS)

    Schweitz, J.P.; Seveon, J.J.

    1987-11-01

    The lessons drawn from experience led EdF to define in 1980 a national specification standard, to be applied to the first standardized series of 900 MWe units and to be adapted to the later 1300 MWe units. This document is periodically revised, every two years or so, to take into account new trends in safety thinking and lessons learnt from operating experience. In this paper we present the main developments in the field of technical specifications, particularly: the definition of rules applicable in the event of unavailability of safety-related equipment, the integration of plant unit operating feedback for specifications optimization

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

  6. Technical co-operation report for 1997. Report by the Director General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    This report covers the IAEA Technical Co-operation (TC) activities during 1997, gives examples of the most significant accomplishments during the year and sets out the status of resources and delivery of the TC programme. The document outlines the steps taken to strengthen planning, design, monitoring and evaluation of TC projects. It also describes how the programme's operational base is being broadened to form new partnerships, using Country Programme Frameworks and Thematic Planning to meet the Member States' priority needs and expand project impact.

  7. Technical co-operation report for 1997. Report by the Director General

    International Nuclear Information System (INIS)

    1998-08-01

    This report covers the IAEA Technical Co-operation (TC) activities during 1997, gives examples of the most significant accomplishments during the year and sets out the status of resources and delivery of the TC programme. The document outlines the steps taken to strengthen planning, design, monitoring and evaluation of TC projects. It also describes how the programme's operational base is being broadened to form new partnerships, using Country Programme Frameworks and Thematic Planning to meet the Member States' priority needs and expand project impact

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

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

    International Nuclear Information System (INIS)

    1996-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1993-01-01

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

  17. Report on research cooperation for developing a simple operation type electronics design and production supporting system in fiscal 1998 (committee activity report); 1998 nendo 'kan'i sosagata denshi sekkei seisan shien system no kaihatsu ni kansuru kenkyu kyoryoku' ni kansuru hokokusho. Iinkai katsudo kiroku

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Research cooperation is being promoted on a simple operation type electronics design and production supporting information system to assist the information using efforts in Asian countries. The cooperation is made jointly with five countries, namely, China, Indonesia, Malaysia, Singapore and Thailand. Fiscal 1998, falling under the final fiscal year, summarized the achievements and the committee activities. In order to promote research and development of automobiles and the components thereof, the WG-I, composed of committee members having professional knowledge, has deliberated specific research and development items, promotion of the research and development, technical problems, and promotion of joint research and development with other countries. The WG-II has made similar discussions on household electric appliances and the components thereof. The MATIC technical committee is composed of chiefs of the working groups and the responsible persons for system development. The committee discussed technical problems common to the working groups in promoting the projects, and made deliberations and adjustments on methods for promoting the research cooperation among the overseas countries. The cooperation promoting committee is composed of Japanese researchers and representatives of research institutes in other countries, and discussed how to move forward and adjust the research cooperation themes. (NEDO)

  18. Report on research cooperation for developing a simple operation type electronics design and production supporting system in fiscal 1998 (committee activity report); 1998 nendo 'kan'i sosagata denshi sekkei seisan shien system no kaihatsu ni kansuru kenkyu kyoryoku' ni kansuru hokokusho. Iinkai katsudo kiroku

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Research cooperation is being promoted on a simple operation type electronics design and production supporting information system to assist the information using efforts in Asian countries. The cooperation is made jointly with five countries, namely, China, Indonesia, Malaysia, Singapore and Thailand. Fiscal 1998, falling under the final fiscal year, summarized the achievements and the committee activities. In order to promote research and development of automobiles and the components thereof, the WG-I, composed of committee members having professional knowledge, has deliberated specific research and development items, promotion of the research and development, technical problems, and promotion of joint research and development with other countries. The WG-II has made similar discussions on household electric appliances and the components thereof. The MATIC technical committee is composed of chiefs of the working groups and the responsible persons for system development. The committee discussed technical problems common to the working groups in promoting the projects, and made deliberations and adjustments on methods for promoting the research cooperation among the overseas countries. The cooperation promoting committee is composed of Japanese researchers and representatives of research institutes in other countries, and discussed how to move forward and adjust the research cooperation themes. (NEDO)

  19. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1992-01-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

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

    International Nuclear Information System (INIS)

    1994-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

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

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

    International Nuclear Information System (INIS)

    1998-11-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  17. The Agency's technical co-operation activities in 1985. Report by the Director General

    International Nuclear Information System (INIS)

    1986-08-01

    Although total resources and disbursements were higher in 1985 than in previous years, the growth rates for both declined somewhat. New resources for the Technical Assistance and Co-operation Fund (TACF) increased by 13%, the TACF accounting for over 66% of all technical co-operation resources in 1985. Pledges made towards the 1985 target for voluntary contributions to the TACF came close to 90% of the target. Although a significant loss on exchange had to be absorbed by the Fund, 96.9% of the target was covered thanks to additional income. Although extrabudgetary resources declined in 1985, they still accounted for one fifth of all technical assistance resources. There was a significant increase in in-kind contributions; this was attributable to the support for non-destructive testing training in Latin America given by Canada, which was the second largest donor of in-kind assistance after the United States. UNDP resources rose very slightly. With UNDP's new five-year programming cycle beginning in 1987, there may be further increases if new projects are identified and timely action taken. New information on implementation expressed as net expenditure and net expenditure rates has been introduced in the form of Expenditure Summaries I, II and III, which provide a more precise picture of performance by fund, geographic area, programme component, field of activity and technical Division. Net expenditure against all funds stood at 57.9%. Net expenditure against the TACF was 66.3%. As UNDP resources and funds in trust account for relatively small shares of the programme, their utilization does not influence the overall net expenditure rate significantly. However, the slow utilization of extrabudgetary resources did have an adverse effect on programme performance as a whole. Net expenditures from the TACF continued to increase at a higher rate than resources, so that the unobligated balance declined for the second consecutive year. In the past, the growing unobligated

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

    International Nuclear Information System (INIS)

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  20. The Agency's Technical Co-operation activities in 1986. Report by the Director General

    International Nuclear Information System (INIS)

    1987-08-01

    During 1986, a total of 854 projects were operational and 71 training courses were held. These activities involved 1930 expert assignments. In addition, 937 persons received training under the fellowship programme. Performance indicators (non-financial) are given in Part II of this report (Sections B and C) in order to provide some impression of the increase in implementation actions related to the delivery of a growing programme. Although total resources were higher in 1986 than in previous years, the overall growth rate declined further while new obligations and disbursements increased steeply. The near-stagnation in the net expenditure rate for Technical Assistance and Co-operation Fund (TACF) resources which occurred in 1985 prompted close monitoring and follow-up measures in 1986. These actions led to an all-time high TACF net expenditure rate, namely 75.7%, in 1986. As the TACF represented 71% of all technical co-operation resources, overall programme performance in terms of net expenditure reached 67.6%, which is also the highest rate ever recorded. TACF resources increased by 11%. Pledges and miscellaneous income covered 92.7% of the target. The percentage attainment of the target has been declining since 1983. As actual disbursements against the TACF increased at a much higher rate than new resources, the unobligated balance decreased to the extent that striving for even higher net expenditure rates would no longer be consistent with judicious resource management. The share of extrabudgetary funds in the programme declined: they accounted for 14.5% of the resources and 12.6% of the disbursements in 1986. The Federal Republic of Germany became the largest contributor of extrabudgetary funds. Special attention will be given to the utilization of these resources so that delivery rates can be improved. As anticipated, UNDP's share in resources and disbursements increased and several new large-scale projects were approved. In-kind assistance continued to play a

  1. 72201 - Temporary reduction of resources for technical infrastructure (TI) operation (ex TCR)

    CERN Multimedia

    Peter Sollander

    2005-01-01

    For a period of two years starting on 1 April 2005, the technical infrastructure will be supervised by a single TI operator rather than two. Initially, this operator will not be able to leave the control room for on-site interventions. Only stand-by staff will be available for breakdown repairs and, as a result, intervention times outside normal working hours are liable to increase. Response times on the 72201 phone number may similarly increase. All requests for breakdown repairs may be sent to the new e-mail address: service-ti@cern.ch; the old address - tcr@cern.ch - will stay in operation. Thank you for your understanding. Peter Sollander AB/OP/TI

  2. Flight Technical Error Analysis of the SATS Higher Volume Operations Simulation and Flight Experiments

    Science.gov (United States)

    Williams, Daniel M.; Consiglio, Maria C.; Murdoch, Jennifer L.; Adams, Catherine H.

    2005-01-01

    This paper provides an analysis of Flight Technical Error (FTE) from recent SATS experiments, called the Higher Volume Operations (HVO) Simulation and Flight experiments, which NASA conducted to determine pilot acceptability of the HVO concept for normal operating conditions. Reported are FTE results from simulation and flight experiment data indicating the SATS HVO concept is viable and acceptable to low-time instrument rated pilots when compared with today s system (baseline). Described is the comparative FTE analysis of lateral, vertical, and airspeed deviations from the baseline and SATS HVO experimental flight procedures. Based on FTE analysis, all evaluation subjects, low-time instrument-rated pilots, flew the HVO procedures safely and proficiently in comparison to today s system. In all cases, the results of the flight experiment validated the results of the simulation experiment and confirm the utility of the simulation platform for comparative Human in the Loop (HITL) studies of SATS HVO and Baseline operations.

  3. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques [Idaho National Lab. (INL), Idaho Falls, ID (United States); Forester, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gertman, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Medema, Heather [Idaho National Lab. (INL), Idaho Falls, ID (United States); Persensky, Julius [Idaho National Lab. (INL), Idaho Falls, ID (United States); Whaley, April [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-08-01

    This report presents preliminary research results from the investigation into the development of new models and guidance for Concepts of Operations in advanced small modular reactor (AdvSMR) designs. AdvSMRs are nuclear power plants (NPPs), but unlike conventional large NPPs that are constructed on site, AdvSMRs systems and components will be fabricated in a factory and then assembled on site. AdvSMRs will also use advanced digital instrumentation and control systems, and make greater use of automation. Some AdvSMR designs also propose to be operated in a multi-unit configuration with a single central control room as a way to be more cost-competitive with existing NPPs. These differences from conventional NPPs not only pose technical and operational challenges, but they will undoubtedly also have regulatory compliance implications, especially with respect to staffing requirements and safety standards.

  4. Report on system operation - A background report prepared by the Nordel Operation Committee/OPG in the Nordel project on enhancing efficient functioning of the Nordic electricity market

    International Nuclear Information System (INIS)

    2004-12-01

    This report contains the operation procedures in extreme situations and lessons learned from blackouts, based on a mandate given by the Operations Committee. Nordic TSOs have had common rules and principles for system operation i.e. System Operation Agreement since the late 1990s. The rules have been revised according to the system security and market changes and needs. The collaboration between system operators is regular and fruitful. The knowledge and capability to manage extreme situations of the Nordic power system has continuously increased and the recent blackouts did not show major deficiencies in operation practices. Regardless of the existing good collaboration it is important to continue development in the future in order to ensure high system security. Important development areas are security of reserve supervision and coordination of calculation procedures for transmission limits, enhancement of data exchange routines between control centres in order to improve the overview of the system security within the Nordic power system. More extensive coordination of outage planning processes will further improve the system security. Continuously training of operational staff is important to be able to manage different situations and disturbances efficiently. (BA)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

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

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

    International Nuclear Information System (INIS)

    1996-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

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

  8. 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

  9. Mechanical properties of self-compacting concrete state-of-the-art report of the RILEM technical committee 228-MPS on mechanical properties of self-compacting concrete

    CERN Document Server

    Schutter, Geert

    2014-01-01

    The State-of-the-Art Report of RILEM Technical Committee 228-MPS on Mechanical properties of Self-Compacting Concrete (SCC) summarizes an extensive body of information related to mechanical properties and mechanical behaviour of SCC. Due attention is given to the fact that the composition of SCC varies significantly. A wide range of  mechanical properties are considered, including compressive strength, stress-strain relationship, tensile and flexural strengths, modulus of elasticity, shear strength, effect of elevated temperature, such as fire spalling and residual properties after fire, in-situ properties, creep, shrinkage, bond properties, and structural behaviour. A chapter on fibre-reinforced SCC is included, as well as a chapter on specialty SCC, such as light-weight SCC, heavy-weight SCC, preplaced aggregate SCC, special fibre reinforced SCC, and underwater concrete.

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

    International Nuclear Information System (INIS)

    Baekelandt, Luc

    2000-01-01

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

  11. Safe operation of critical assemblies and research reactors. Code of practice and Technical appendix. 1971 ed

    International Nuclear Information System (INIS)

    Cox, J.

    1971-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Critical Assemblies and Research Reactors, prepared as a result of a meeting of experts which took place in Vienna on 20-24 May 1968. The Code has been prepared by the International Atomic Energy Agency in co-operation with the World Health Organization, and its publication is sponsored by both organizations. In addition, the Code was approved by the Board of Governors of the International Atomic Energy Agency on 16 December 1968 as part of the Agency's safety standards, which are applied to operations undertaken by Member States with the assistance of the Agency. The Board, in approving the publication of the present book, also recommended Member States to take the Code into account in the formulation of national regulations and recommendations. The second part of the book is a Technical Appendix to give information and illustrative samples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. An extensive Bibliography, amplifying the Technical Appendix, is included at the end.

  12. The Agency's Technical Co-operation programme in Chile, 1981-1991. Country programme evaluation

    International Nuclear Information System (INIS)

    1992-01-01

    Agency support for nuclear activities in Chile dates back to the early 1960s. During the last ten years, the period covered by this evaluation, this support has considerably expanded. In the period 1981-1991, 62 Agency projects with allotments amounting to over $7 million were completed or are under implementation. Through this co-operation Chile has received 360 man-months of expert services, $3.4 million worth of equipment, and 105 fellowships for some 390 man-months of training. In addition, 262 Chileans attended 219 Agency regional and interregional training courses, and Chilean institutions were awarded 40 research contracts worth over $325,000. This evaluation covers ten years of Agency technical co-operation with Chile, during which 35 projects were completed and 27 are still being implemented. Eight major sectors received assistance: general atomic energy development; nuclear physics; nuclear raw materials; nuclear engineering and technology; nuclear techniques in agriculture; nuclear medicine; hydrology; and nuclear safety. The evaluation concluded that, overall, the Agency's technical co-operation activities have, in keeping with the national priorities concerning peaceful nuclear applications, contributed substantially to the establishment of Chile's nuclear scientific and technical infrastructure, and played a major role in Chile's efforts to introduce nuclear applications in a number of sectors of the economy, with many benefits for broader national development objectives. Another strength of the Agency's programme with Chile is the high level of commitment and dedication that was noted in the great majority of recipient institutions, and in particular at the Comision Chilena de Energia Nuclear, CChEN. Mention should also be made of the fact that bureaucracy appears to be less severe than in some other developing countries, and that constraints that frequently affect other countries, such as insufficient counterpart commitment and lack of continuity of

  13. Environmental-technical aspects of the operation of the accelerator at NIKHEF-K

    International Nuclear Information System (INIS)

    Post, J.C.

    1982-12-01

    This report discusses those technical aspects of the operation of the Medium Energy Accelerator at NIKHEF-K which affect the environment. The accelerator produces an electron beam with a maximum capacity of 300 kW and, as by-products, intense gamma and neutron radiations. These radiations can contaminate components of the accelerator and the direct surroundings. The electron beam can also generate ozone in the air. The accelerator produces a small quantity of radioactive waste itself and research in the chemistry department also leads to the production of radioactive waste. These wastes are stored temporarily and transported for treatment/storage elsewhere in Holland once a year. (Auth.)

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

    International Nuclear Information System (INIS)

    2016-08-01

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

  15. Technical Aspect for Operating Portable Prompt Gamma Neutron Activation Analysis (PGNAA) on Terengganu Inscribed Stone

    International Nuclear Information System (INIS)

    Rasif Mohd Zain; Hearie Hassan; Roslan Yahya

    2015-01-01

    Prompt Gamma Neutron Activation analysis (PGNAA) is a type of neutron activation analysis which can determined element with nearly no gamma ray decay after being irradiated by neutron sourced. Thus, element that cannot be determined by the conventional NAA for example H, B, N, Si and Cd, can be determine by PGNAA. This paper focuses on the technical working procedure for operating portable PGNAA in field work. The device is designed as a portable non-destructive investigation tool applying an isotopic neutron source (Cf-252) and a gamma-ray spectroscopy system for in-situ investigation. The studied have been carried out on Terengganu inscribed stone at Terengganu State Museum. (author)

  16. Committee on Atomic, Molecular, and Optical Sciences (CAMOS). Technical progress report ampersand continuation proposal, February 1, 1993--January 31, 1994

    International Nuclear Information System (INIS)

    Taylor, R.D.

    1997-01-01

    The Committee on Atomic, Molecular and Optical Sciences (CAMOS) of the National Research Council (NRC) is charged with monitoring the health of the field of atomic, molecular, and optical (AMO) science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special symposia are among the mechanisms used by the CAMOS to meet its charge. This progress report presents a review of CAMOS activities from February 1, 1993 to January 31, 1994. The details of prior activities are discussed in earlier progress reports. This report also includes the status of activities associated with the CAMOS study on the field that is being conducted by the Panel on the Future of Atomic, Molecular, and Optical Sciences (FAMOS). During the above period, CAMOS has continued to track and participate in, when requested, discussions on the health of the field. Much of the perspective of CAMOS has been presented in the recently-published report Research Briefing on Selected Opportunities in Atomic, Molecular, and Optical Sciences. That report has served as the basis for briefings to representatives of the federal government as well as the community-at-large. In keeping with its charge to monitor the health of the field, CAMOS launched a study designed to highlight future directions of the field

  17. The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency. Latest Status

    International Nuclear Information System (INIS)

    1979-03-01

    The Revised Guiding Principles and General Operating Rules to Govern the Provision of Technical Assistance by the Agency were approved by the Board of Governors on 21 February 1979. The test is reproduced herein for the information of all Members. The provisions established by the Board of Governors on 24 September 1977 for the application of safeguards in relation to the granting of technical assistance are also reproduced in the Annex to the Revised Guiding Principles and General Operating Rules.

  18. IAEA's technical co-operation programme and its role in assisting member states in the safe utilisation of nuclear power

    International Nuclear Information System (INIS)

    Reed, J.

    2000-01-01

    In this contribution the author deals with the technical co-operation projects of the IAEA. The Agency's technical co-operation programme is a most welcome mechanism for the transfer of nuclear technology, and to developing countries it is certainly the most attractive side of the Agency, since it is through this programme that the IAEA can contribute to the solution of their problems through the provision of know-how, technology and training. (authors)

  19. Characterization and management of radioactive sodium and other reactor components as input data for the decommissioning of liquid metal-cooled fast reactors. A compilation of data produced of data produced by members of the IAEA technical working group on fast reactors (TWG-FR) at two consultancies and one technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    A number of liquid metal cooled fast reactors (LMFRs) are in operation and, some have already been shut down; other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of reactors at the plant design and construction stage. It is with this focus that the Technical Working Group on Fast Reactors (TWGFR) recommended that the IAEA organize the exchange of information on LMFRs decommissioning technology. It was pointed out that the decommissioning of small sodium-cooled reactors has shown that there are two basic differences between thermal and fast reactors decommissioning: on the one side, the treatment and disposal of radioactive sodium coolant, and on the other side, the management of reactor components, for which the structural materials are activated in depth by fast neutrons. To this end, a Technical Committee Meeting on Sodium Removal and Disposal from LMFRs in Normal Operation and in the framework of Decommissioning (Aix-en-Provence, France, November 1997) and two Consultancies on Decommissioning of the Kazakh BN-350 LMFR (Vienna, Austria, October 1996; Obninsk, Russian Federation, February 1998) were convened by the IAEA. These Meetings brought together a group of experts from France, Russia, Kazakhstan, the UK, and the USA to exchange information on, and to review current technical knowledge and experience in the management of radioactive coolant and reactor components following closing of LMFRs, as well as their design features and operating experience relevant for decommissioning procedures. The report provides general and detailed information on activation characteristics of the primary coolant; treatment and disposal of the spent sodium; removal of the residual sodium deposits and decontamination; the activation characteristics of the reactor components and the management of the latter. The recurring theme is finding

  20. The VGB 'Plant Engineering' Special Committee

    International Nuclear Information System (INIS)

    Pamme, Hartmut

    2009-01-01

    The ''Plant Engineering'' Special Committee deals with technical issue of reliable and safe operation of German nuclear power plants. The activities of the expert network of VGB PowerTech e.V. serve to find technical solutions to questions of detail and, in addition, harmonize the work of more than 30 working parties of the Nuclear Power Plants Competence Center. This function makes the Committee also a hub of nuclear activities in VGB. Besides consulting on problems of plant technology, the Committee now also processes or writes opinions and decisions in particular to help industries in negotiating with authorities, the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU), and other institutions. (orig.)