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Sample records for technical activities committee

  1. 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

  2. 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.

  3. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    1999-01-01

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

  4. ITER technical advisory committee meeting

    International Nuclear Information System (INIS)

    Fujiwara, M.

    2001-01-01

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

  5. 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'

  6. 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...

  7. 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

  8. 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.

  9. 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.

  10. 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...

  11. Activities of the research committee

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, A.; Shirai, T.; Nakagawa, M.; Osugi, T.; Ikeda, Y.; Ishida, T.; Shimazaki, J. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-01-01

    The department of Nuclear Energy System serves as a secretarial of the following four research committees organized by JAERI; Japanese Nuclear Data Committee, Atomic and Molecular Data Research Committee, Research Committee on Reactor Physics and Research Committee on Marine Reactors. The purpose and the expected task of each committee are summarized here. The detailed activities of each committee are presented in this paper. (author)

  12. 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...

  13. 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…

  14. 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…

  15. 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

  16. 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…

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

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

    Science.gov (United States)

    2011-05-20

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

  14. 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...

  15. 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...

  16. 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.

  17. 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.)

  18. Summary of IAEA technical committee meeting on impurity control

    International Nuclear Information System (INIS)

    Itoh, Kimitaka.

    1989-03-01

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

  19. 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...

  20. 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.)

  1. 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...

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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...

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

    Science.gov (United States)

    2010-07-13

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

  8. 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...

  9. 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...

  10. 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...

  11. 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...

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

    Science.gov (United States)

    2011-10-19

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

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

    Science.gov (United States)

    2011-07-07

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

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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

  1. 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

  2. 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...

  3. 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

  4. TECHNICAL ENGINEERS AND ADMINISTRATIVE CARRERS COMMITTEE (TEACC)

    CERN Multimedia

    Division des ressources humaines

    2000-01-01

    1.\tComposition and mandateTEACC is composed of a Chairman and of other members of Career Path IX level, nominated by the Leader of Human Resources Division.TEACC examines proposals for change from Career Path VI to Career Path VII and makes its recommendations to the Leader of Human Resources Division.2.\tProcedureProposals may be made to TEACC in the following situations:2.1\tThe staff member possesses a recognised university diploma and is reassigned to a post considered by the division as corresponding to Career Path VII. The proposal may be made after a minimum of one year in the new activity.2.2\tThe staff member does not possess a recognised university diploma and is transferred or reassigned to, or already occupying, a post previously recognised as corresponding to Career Path VII, or considered by the division as having evolved to this level. The proposal may be made, within the annual staff review, when the staff member has occupied the current post for a minimum of one year....

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. Technical activities, 1990: Surface Science Division

    International Nuclear Information System (INIS)

    Powell, C.J.

    1991-05-01

    The report summarizes technical activities and accomplishments of the NIST Surface Science Division during Fiscal Year 1990. Overviews are presented of the Division and of its three constituent groups: Surface Dynamical Processes, Thin Films and Interfaces, and Surface Spectroscopies and Standards. These overviews are followed by reports of selected technical accomplishments during the year. A summary is given of Division outputs and interactions that includes lists of publications, talks, committee assignments, seminars (including both Division seminars and Interface Science seminars arranged through the Division), conferences organized, and a standard reference material certified. Finally, lists are given of Division staff and of guest scientists who have worked in the Division during the past year

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  11. Technical 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.

  12. 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

  13. 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

  14. 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

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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.

  15. 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

  16. ITER EDA technical activities

    International Nuclear Information System (INIS)

    Aymar, R.

    1998-01-01

    Six years of technical work under the ITER EDA Agreement have resulted in a design which constitutes a complete description of the ITER device and of its auxiliary systems and facilities. The ITER Council commented that the Final Design Report provides the first comprehensive design of a fusion reactor based on well established physics and technology

  17. 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

  18. Technical planning activity: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements.

  19. Technical planning activity: Final report

    International Nuclear Information System (INIS)

    1987-01-01

    In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements

  20. 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.

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. 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).

  6. 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

  7. 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...

  8. 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

  9. 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...

  10. 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.

  11. 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

  12. 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

  13. 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

  14. 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...

  15. 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.

  16. French butane propane committee. 2003 activity report

    International Nuclear Information System (INIS)

    2003-01-01

    This activity report presents the French butane-propane committee (CFBP), an association for the promotion of liquefied petroleum gases (LPG), the characteristics of LPG fuels, the LPG market and its evolution, the CFBP's missions and the 2003 highlights: representation of subscribing companies, participation to standardization works, making techniques and regulations change, improving the safety of equipments and installations, training and information, promoting LPG products. (J.S.)

  17. French butane propane committee. 2004 activity report

    International Nuclear Information System (INIS)

    2004-01-01

    This activity report presents the French butane-propane committee (CFBP), an association for the promotion of liquefied petroleum gases (LPG), the characteristics of LPG fuels, the LPG market and its evolution, the CFBP's missions and the 2004 highlights: representation of subscribing companies, participation to standardization works, making techniques and regulations change, improving the safety of equipments and installations, training and information, promoting LPG products. (J.S.)

  18. 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…

  19. 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...

  20. 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.

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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)

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

    International Nuclear Information System (INIS)

    1997-01-01

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

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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…

  13. 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...

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

    Science.gov (United States)

    2011-01-04

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

  15. 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...

  16. 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...

  17. 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

  18. 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…

  19. 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

  20. 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

  1. 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.

  2. 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

  3. 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.

  4. 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).

  5. 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

  6. 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.)

  7. 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

  8. 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)

  9. 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.

  10. 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.

  11. 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.

  12. International Project Management Committee: Overview and Activities

    Science.gov (United States)

    Hoffman, Edward

    2010-01-01

    This slide presentation discusses the purpose and composition of the International Project Management Committee (IMPC). The IMPC was established by members of 15 space agencies, companies and professional organizations. The goal of the committee is to establish a means to share experiences and best practices with space project/program management practitioners at the global level. The space agencies that are involved are: AEB, DLR, ESA, ISRO, JAXA, KARI, and NASA. The industrial and professional organizational members are Comau, COSPAR, PMI, and Thales Alenia Space.

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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...

  18. 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)

  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. 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

  1. Committees review activities at December meetings

    Science.gov (United States)

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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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.

  9. 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

  10. 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.

  11. ITER co-ordinated technical activities

    International Nuclear Information System (INIS)

    2001-01-01

    As agreed upon between the ITER Engineering Design Activities (EDA) Parties 'Co-ordinated Technical Activities' (CTA) means technical activities which are deemed necessary to maintain the integrity of the international project, so as to prepare for the ITER joint implementation. The scope of these activities includes design adaptation to the specific site conditions, safety analysis and licensing preparation that are based on specific site offers, evaluation of cost and construction schedule, preparation of procurement documents and other issues raised by the Parties collectively, whilst assuring the coherence of the ITER project including design control

  12. 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

  13. 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.

  14. 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

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

    International Nuclear Information System (INIS)

    1998-03-01

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

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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.)

  1. 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

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

    International Nuclear Information System (INIS)

    1997-05-01

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

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

    International Nuclear Information System (INIS)

    2000-10-01

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

  4. 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.)

  5. 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.

  6. 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)

  7. Final Technical Report Transport Task Force Activities

    International Nuclear Information System (INIS)

    P.W. Terry

    2006-01-01

    The Transport Task Force has functioned as the primary scientific organization in the area of magnetic-fusion confinement and transport since its inception in 1988. It has defined and set research directions, coordinated broad research efforts, advocated new funding initiatives, and created a highly successful and widely admired interactive culture between experiment, theory and modeling. The Transport Task Force carries out its activities under the direction of its chair and the Executive Committee. The Executive Committee is comprised of the leaders and deputy leaders of the scientific working groups. The working groups are structured and organized according to research needs and priorities and have been organized around the areas of Core Transport, H Mode and Pedestal, Fast Particle Transport, Transient Transport Phenomena, and Modeling and Simulation. A steering committee provides advise on TTF activities. Further information on the working groups and the structure and management of the TTF can be found at http://psfcwww2.psfc.mit.edu/ttf/index.html. The TTF holds an annual workshop. A summary of the workshops held during the period of this report is given in Appendix I. During the period of this report the Transport Task Force was involved in several significant activities. Foremost of these was a sweeping review of the status of transport science, the key research tasks for progress during the next 5-10 years, and a proposal for a funding initiative to ensure application of adequate resources to these problems. The conclusions of this study were incorporated into a white paper, which is copied below in Appendix II. Other significant activities have included the introduction of an extended, ongoing discussion on verification and validation as a requisite for defining and codifying the path toward predictive capability, the orchestration of a gradual shift of focus from ion thermal confinement to electron thermal confinement, and a joining of efforts on edge

  8. 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...

  9. 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...

  10. Activities on covariance estimation in Japanese Nuclear Data Committee

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    Described are activities on covariance estimation in the Japanese Nuclear Data Committee. Covariances are obtained from measurements by using the least-squares methods. A simultaneous evaluation was performed to deduce covariances of fission cross sections of U and Pu isotopes. A code system, KALMAN, is used to estimate covariances of nuclear model calculations from uncertainties in model parameters. (author)

  11. Report of activities of the Japanese Nuclear Data Committee

    International Nuclear Information System (INIS)

    1977-01-01

    A progress report of the Japanese Nuclear Data Committee for the period of April 1, 1975 to March 31, 1977 is presented with emphasis on the topics of Japanese Evaluated Nuclear Data Library, version I(JENDL-1). Activities of working groups are also reported briefly. (auth.)

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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...

  17. 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

  18. 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

  19. 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...

  20. 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

  1. 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

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

    International Nuclear Information System (INIS)

    1997-10-01

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

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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

  8. 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...

  9. 34 CFR 300.119 - Technical assistance and training activities.

    Science.gov (United States)

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false Technical assistance and training activities. 300.119... Technical assistance and training activities. Each SEA must carry out activities to ensure that teachers and....114; and (b) Are provided with technical assistance and training necessary to assist them in this...

  10. 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....

  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. [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.

  13. 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

  14. 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

  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. 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...

  17. Initial activities of the ITER Management Advisory Committee

    International Nuclear Information System (INIS)

    Yoshikawa, Masaji

    1994-01-01

    The first ITER Council meeting (IC-1) took place in Vienna Austria at the International Atomic Energy Agency (IAEA) headquarters on 10-11 September, 1992. At that meeting the Council appointed Dr. Masaji Yoshikawa as Chair of the Management Advisory Committee (MAC). The Parties designated the members of MAC. The first MAC meeting was held at the ITER CoCenter, Naka, Japan, on 1-3 December 1992 and reviewed its tasks as charged by the Council. In accordance with Article 7 of the ITER EDA Agreement, it is the responsibility of MAC to report to and advise the ITER Council in management and administrative matters, including finance, personnel and task assignment. Also, in accordance with Article 11 of the ITER EDA Agreement, the MAC advises the ITER Council on the Work Program developed by the Director. The Work Program is to contain a detailed list of specific tasks, including a technical description of each task, and the assignment of the specific tasks to each of the Home Teams and the Joint Central Team (JCT), and a flow chart of the specific tasks during the whole EDA. According to Section 3 of Protocol 1, the tasks are to be performed by the Home Teams; task descriptions are to contain a detailed technical description of each task and an indication of the facilities and background information needed for its implementation

  18. Activities of the O&M committee history & future perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Poulis, D.S.

    1996-12-01

    This paper gives an overview of the Committee on Operation and Maintenance of Nuclear Power Plants, hereafter referred to as the O&M Committee, formed in June 1975 when the American National Standard Institute`s Committee on Reactor Plants and their Maintenance was disbanded. The O&M Committee`s history, structure, current focus and future perspectives will be presented. The purpose of this paper is to give information to industry and the public of the Committee`s on-going effort to make accurate and timely responses to the needs of the nuclear industry.

  19. 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...

  20. 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...

  1. 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

  2. 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

  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. 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

  5. 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...

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

    Science.gov (United States)

    2010-08-03

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

  7. DOE technical standards list: Directory of DOE and contractor personnel involved in non-government standards activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The body of this document contains a listing of DOE employees and DOE contractors who have submitted form DOE F 1300.2, Record of Non-Government Standards Activity, which is attached to the end of this document. Additional names were added from rosters supplied by non-Government standards bodies. The committees or governing bodies in which the person participates is listed after each name. An asterisk preceding the committee notation indicates that the person has identified himself or herself as the DOE representative on that committee. Appendices to this document are also provided to sort the information by the parent employment organization, by non-Government standards activity, and by the proper names of the non-Government standards organizations and committees. DOE employees and contractors listed in this technical standards list are those recorded as of May 1, 1999.

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

    International Nuclear Information System (INIS)

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

    2010-02-01

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

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. Activities of the ANS special committee on nuclear nonproliferation

    Energy Technology Data Exchange (ETDEWEB)

    Buckner, M.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Sanders, T.L. [Sandia National Labs., Albuquerque, NM (United States)

    2001-07-01

    The American Nuclear Society (ANS) Special Committee on Nuclear Nonproliferation (SCNN) believes that to reverse current trends, U.S. policy must revisit the fundamental premise of Atoms for Peace: A collaborative nuclear enterprise enhances rather than diminishes national security. To accomplish this, the U.S. Government must develop an integrated policy on energy, nuclear technology, and national security. The policy must recognize that these are interrelated and that an integrated policy will require substantial investments in nuclear research and development and in nuclear education. This paper describes the current activities of the SCNN to heighten awareness of nonproliferation issues for decision makers and ANS members, and alert them to the need for action to resolve these concerns. (author)

  15. Activities of the ANS special committee on nuclear nonproliferation

    International Nuclear Information System (INIS)

    Buckner, M.R.; Sanders, T.L.

    2001-01-01

    The American Nuclear Society (ANS) Special Committee on Nuclear Nonproliferation (SCNN) believes that to reverse current trends, U.S. policy must revisit the fundamental premise of Atoms for Peace: A collaborative nuclear enterprise enhances rather than diminishes national security. To accomplish this, the U.S. Government must develop an integrated policy on energy, nuclear technology, and national security. The policy must recognize that these are interrelated and that an integrated policy will require substantial investments in nuclear research and development and in nuclear education. This paper describes the current activities of the SCNN to heighten awareness of nonproliferation issues for decision makers and ANS members, and alert them to the need for action to resolve these concerns. (author)

  16. 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.

  17. 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

  18. 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.

  19. 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

  20. 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...

  1. 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...

  2. Report of the summative evaluation by the advisory committee on research support and collaborative activities

    International Nuclear Information System (INIS)

    2005-03-01

    The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an Advisory Committee on Research Support and Collaborative Activities in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Research Support and Collaborative Activities evaluated the adequacy of the plans of research support and collaborative activities to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of nine specialists from outside the JAERI conducted its activities from June 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Advisory Committee meeting which was held on July 21, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Research Support and Collaborative Activities. (author)

  3. 75 FR 4904 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2010-01-29

    ... amend regulations protecting persons who work on, under, or between rolling equipment; and persons...-7257] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad... Committee (RSAC) Working Group Activities. SUMMARY: The FRA is updating its announcement of RSAC's Working...

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

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

  11. Final Progress Report for the activity called AMO2010 committee

    Energy Technology Data Exchange (ETDEWEB)

    Donald Shapero; Michael Moloney

    2006-12-31

    The committee was charged to produce a comprehensive report on the status of AMO Science. The committee was charged to produce a report that: 1. Reviewed the field of AMO science, emphasize recent accomplishments, and identify new opportunities and compelling scientific questions; 2. Identified the impact of AMO science on other scientific fields, emerging technologies, and national needs; 3. Identified future workforce, societal and educational needs for AMO science; and 4. Made recommendations on how the US research enterprise might realize the full potential of AMO science. The committee also produced an intermediate report addressing key research issues and themes facing the research community.

  12. 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

  13. 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)

  14. 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.

  15. 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.

  16. 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

  17. 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

  18. 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. .

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

    International Nuclear Information System (INIS)

    2010-01-01

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

  20. 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.

  1. 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

  2. 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.

  3. 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

  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. Control of heavy loads at nuclear power plants: Resolution of Generic Technical Activity A-36. Technical report

    International Nuclear Information System (INIS)

    George, H.J.

    1980-07-01

    This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-36, Control of Heavy Loads Near Spent Fuel. Generic Technical Activity A-36 is one of the generic technical subjects designated as unresolved safety issues pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical studies and evaluations performed by the NRC staff, the staff's guidelines based on these studies, and the staff's plans for implementaton of its technical guidelines

  6. HCTISN - High Committee for transparency and information on nuclear safety - Annual activity report - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This activity report first describes the Committee operation (missions, composition, organization and operation rules, and means). Then, it reports the Committee's activity during 2011: works related to the Fukushima accident, report and recommendations on transparency and secrets in the nuclear sector, report and recommendations on the search for a storage site for long life and low activity wastes, meetings and work-groups, and visits

  7. BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of generic technical activity A-10. Technical report

    International Nuclear Information System (INIS)

    Snaider, R.

    1980-11-01

    This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-10, 'BWR Nozzle Cracking'. Generic Technical Activity A-10 is one of the generic technical subjects designated as 'unresolved safety issues' pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical issues, the technical studies and analyses performed by the General Electric Company and the NRC staff, the staff's technical positions based on these studies, and the staff's plans for continued implementation of its technical positions. It also provides information for further work to resolve the non-destructive examination issue

  8. 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.

  9. Results of SSTC NRS Scientific and Technical Activities for 2014

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Valyigun, N.P.; Vorobej, I.I.; Kornijevska, O.S.

    2015-01-01

    The paper describes results of SSTC NRS scientific activities for 2014 in basic areas of activities. In particular, it addresses the development of nuclear regulatory control system, reviews, scientific and technical support to the SNRIU oversight function, research ampersand development and analytical efforts as well as scientific information and international activity. First-priority areas for SSTC NRS for the nearest years are identified

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    1995-09-01

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

  12. Opinions expressed by Italian National Advisory Toxicological Committee on some active ingredients of pesticides

    Energy Technology Data Exchange (ETDEWEB)

    Camoni, I [Ist. Superiore di Sanita` , Rome (Italy). Lab. di Tossicologia Applicata

    1996-03-01

    The opinions expressed by the Italian National Advisory Toxicological Committee (CCTN) on some active ingredients of pesticides are presented. Carcinogenic and mutagenic effects of these substances have been examined and, on this basis, an evaluation and relative classification were expressed.

  13. Physics Laboratory technical activities, 1991. Final report

    International Nuclear Information System (INIS)

    Gebbie, K.B.

    1992-02-01

    The report summarizes research projects, measurement method development, calibration and testing, and data evaluation activities that were carried out during calendar year 1991 in the NIST Physics Laboratory. These activities fall in the areas of electron and optical physics, atomic physics, molecular physics, radiometric physics, quantum metrology, ionizing radiation, time and frequency, quantum physics, and fundamental constants

  14. 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

  15. Activities of the research committee on thorium cycle in atomic energy society of Japan

    International Nuclear Information System (INIS)

    Hohki, Shiro

    1985-01-01

    In 1978 the Research Committee on Thorium Cycle was established as one of committees of the Atomic Energy Society of Japan, and the Committee published a report titled 'The Thorium Cycle - Present Status and Future Prospect' in October 1980 as a result of investigations on the status of the thoirum cycle in Japan as well as that in overseas. Based on this investigation, the Committee is intending to evaluate synthetically the thorium utilization in Japan under the prospect for the middle and long term by intensifying the activities of the Committee. Furthermore, from this viewpoint, the author supplements comments on following three points: (1) Reasons why the thorium utilization has not received positive evaluation in Japan; (2) Reasons why Japan has to pay attention to thorium; (3) How the technology on thorium should be developed in Japan. (author)

  16. Active imaging for monitoring and technical diagnostics

    Directory of Open Access Journals (Sweden)

    Marek Piszczek

    2014-08-01

    Full Text Available The article presents the results of currently running work in the field of active imaging. The term active refers to both the image acquisition methods, so-called methods of the spatio-temporal framing and active visualization method applying augmented reality. Also results of application of the HMD and 6DoF modules as well as the experimental laser photography device are given. The device works by methods of spatio-temporal framing and it has been developed at the IOE WAT. In terms of image acquisition - active imaging involves the use of illumination of the observed scene. In the field of information visualization - active imaging directly concerns the issues of interaction human-machine environment. The results show the possibility of using the described techniques, among others, rescue (fire brigade, security of mass events (police or the protection of critical infrastructure as well as broadly understood diagnostic problems. Examples presented in the article show a wide range of possible uses of the methods both in observational techniques and measurement. They are relatively innovative solutions and require elaboration of series of hardware and algorithmic issues. However, already at this stage it is clear that active acquisition and visualization methods indicate a high potential for this type of information solutions.[b]Keywords[/b]: active imaging, augmented reality, digital image processing

  17. Technical activities report: Mechanical development studies

    Energy Technology Data Exchange (ETDEWEB)

    Alexander, W.K.

    1952-05-01

    This monthly progress report covers activities in the following areas: pile control; shielding studies; process tube assembly; pile operating equipment; power recovery; pile piping; and test laboratory. A detailed discussion is given for each topic.

  18. Effects of Man's Activities on the Marine Environment; Committee on Commerce, United States Senate, Ninety-Fourth Congress, First Session. Committee Print.

    Science.gov (United States)

    Congress of the U.S., Washington, DC. Senate Committee on Commerce.

    This report, prepared for the Committee on Commerce and the National Ocean Policy Study Committee, describes many aspects of water pollution, both national and international. Specific sections are devoted to: (1) assessing man's influence on the oceans, (2) activities that generate marine pollution, (3) specific marine pollutants, (4) policy for…

  19. 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

  20. 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

  1. 100 Areas technical activities report, engineers - March 1951

    Energy Technology Data Exchange (ETDEWEB)

    1951-04-01

    This is the monthly 100 areas technical activities report from the engineering division for the month of March 1951. It reports on engineering activities related directly to the different production reactors, and gives progress reports on various engineering projects which are in development by the engineering group.

  2. COMPLEMENTARY EFFECTS IN ACTIVIZATION OF SCIENTIFIC AND TECHNICAL ACTIVITIES IN THE INFORMATION SOCIETY

    Directory of Open Access Journals (Sweden)

    O. Zhylinska

    2016-09-01

    Full Text Available This paper proposes new methodological approaches in the study of development problems of scientific and technical activities in the information society. The essence and economic nature of development scientific and technical activities' from the standpoint of methodological collectivism are disclosed, a new phenomenon intensification of development scientific and technical activities by forming the global networks of scientific and technical knowledge users that provides sharing of the burden of transformation and transaction costs as generation as well as economic implementation of research and technical knowledge across the globe are showed. This study outlines the complementary effects in intensify development of scientific and technological activities components: research and development (RD, training of scientific personnel, provision of scientific and technical services, which generates of world market's complementary goods, being world market of educational services of scientific and technical information, industrial properties, high technology products, venture capital investments and stock market.

  3. 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

  4. 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...

  5. 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

  6. 78 FR 5774 - Materials Technical Advisory Committee; Notice of Partially Closed Meeting

    Science.gov (United States)

    2013-01-28

    .... Remarks from BIS senior management. 3. Presentation by DuPont on the impact of Australia Group and.... 5. Report on regime-based activities. 6. Public comments and new business. 7. Request for volunteers...

  7. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1996-12-01

    The FY 1995 budget summary table for DOE Materials Activities is presented on pages 6-8. Following the budget summary table is a set of detailed program descriptions for the FY 1995 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department A mission statement a budget summary table listing the project titles and FY 1995 funding, and detailed project summaries are presented for each Assistant Secretary office and the Office of Energy Research. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project as appropriate.

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

    International Nuclear Information System (INIS)

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

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

  10. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 1998

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1999-07-31

    The FY 1998 budget summary for DOE Materials Activities is presented on pages 7 and 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 9. Following the budget summary is a set of detailed program descriptions for the FY 1998 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 1998 funding, and detailed project summaries are presented for each Assistant Secretary office and the Office of Energy Research. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  11. On the activities and perspective works of Soviet Scientist Committee for peace against nuclear hazard

    International Nuclear Information System (INIS)

    Velikhov, E.P.

    1986-01-01

    Activities of Soviet Scientists' Committee for peace against nuclear hazard established in May 1983 was considered. Committee efforts are directed at struggle for nuclear weapon destruction, for stopping of all kinds of its tests against disposition of nuclear waepon in space. Soviet scientist report on SDI says that such system may serve not only as defensive means but also as means of destruction of earth, air and other objects and represents the most serious danger. Together with american scientists the Committee investigated ecological consequencies of nuclear war which results strongly impressed all over the world. Attention is paid to prospects in the Committee work related to the development of nuclear weapon destribution procedures as well as procedures and means of controls for destruction and limitation of weapons

  12. 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

  13. 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

  14. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

  16. Environmental Measurements Laboratory fiscal year 1998: Accomplishments and technical activities

    Energy Technology Data Exchange (ETDEWEB)

    Erickson, M.D.

    1999-01-01

    The Environmental Measurements Laboratory (EML) is government-owned, government-operated, and programmatically under the DOE Office of Environmental Management. The Laboratory is administered by the Chicago Operations Office. EML provides program management, technical assistance and data quality assurance for measurements of radiation and radioactivity relating to environmental restoration, global nuclear nonproliferation, and other priority issues for the Department of Energy, as well as for other government, national, and international organizations. This report presents the technical activities and accomplishments of EML for Fiscal Year 1998.

  17. 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.

  18. 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

  19. Energy Materials Coordinating Committee (EMaCC): Fiscal year 1986, Annual technical report

    International Nuclear Information System (INIS)

    1987-05-01

    The first part of the Program Descriptions consists of a funding summary for each Assistant Secretary office and the Office of Energy Research. This is followed by a summary of project titles and objectives, including the program/project manager(s) and principal investigator. The second part of the Program Descriptions consists of more detailed project summaries with project goals and accomplishments. They are for the Offices of Conservation and Renewable Energy, Energy Research, Nuclear Energy, Civilian Radioactive Waste Management, and Fossil Energy. Each of these are numbered for purposes of reference in the Keyword Index. The FY 1986 Budget Summary for materials activities in each of the 29 programs within the DOE are also included

  20. 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

  1. 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.

  2. NASA Space Environments Technical Discipline Team Space Weather Activities

    Science.gov (United States)

    Minow, J. I.; Nicholas, A. C.; Parker, L. N.; Xapsos, M.; Walker, P. W.; Stauffer, C.

    2017-12-01

    The Space Environment Technical Discipline Team (TDT) is a technical organization led by NASA's Technical Fellow for Space Environments that supports NASA's Office of the Chief Engineer through the NASA Engineering and Safety Center. The Space Environments TDT conducts independent technical assessments related to the space environment and space weather impacts on spacecraft for NASA programs and provides technical expertise to NASA management and programs where required. This presentation will highlight the status of applied space weather activities within the Space Environment TDT that support development of operational space weather applications and a better understanding of the impacts of space weather on space systems. We will first discuss a tool that has been developed for evaluating space weather launch constraints that are used to protect launch vehicles from hazardous space weather. We then describe an effort to better characterize three-dimensional radiation transport for CubeSat spacecraft and processing of micro-dosimeter data from the International Space Station which the team plans to make available to the space science community. Finally, we will conclude with a quick description of an effort to maintain access to the real-time solar wind data provided by the Advanced Composition Explorer satellite at the Sun-Earth L1 point.

  3. 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

  4. Focus on the Activity of a Local Ethics Committee in Italy

    Directory of Open Access Journals (Sweden)

    Pamela Barbadoro

    2008-06-01

    Full Text Available

    Background: The continuing evolution of medical treatments and the loss of neutrality of medicine with respect to morality of human values have represented the major tracking elements towards settings of sharing of choices between society and medicine. Several concerns have been raised upon links between pharmaceutical corporations and researchers. Moreover, being in a learning environment, we must pay even more attention to these items because students appear to be at risk for unrecognized influence by marketing efforts. The aim of this study is to focus on the activities of a local ethics committee (LEC and the characteristics of the protocols discussed in an Italian LEC during a three year period (2001-2003.

    Methods: Three years of activity of a LEC were analysed by a questionnaire registering: main sponsorship, setting, technical characteristics of trials, outcome of the submission to the LEC, state of progress. Approved trials were followed-up until April 30th, 2005.

    Results: A total of 345 protocols were discussed. 67.8% (n = 198 of approved protocols were submitted by a pharmaceutical corporation. 72.6% (n = 212 of studies approved in 2001 were still in progress in 2005. 91.3% (n = 73 of closed trials had a pharmaceutical corporation as their main sponsor. None of the submitted studies focused on prevention strategies.

    Conclusions: These results show how important grants offered by pharmaceutical industries are, the efforts spent on therapy and the lack of investors in prevention.

  5. 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

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

    International Nuclear Information System (INIS)

    1985-08-01

    The year 1984 can be described as one during which efforts were made to increase momentum in the development co-operation between the Agency and its Member States while continuing to improve the quality of the technical assistance rendered. For the first time, the adjusted programme exceeded $50 million. During the year, changes were introduced in the administration of the programme in line with recommendations endorsed by the Board in 1983 at the end of its first technical co-operation policy review. In 1984, when the new technical co-operation policies were applied, there were three principal aims. First, the flow of Technical Assistance and Co-operation Fund resources was to be improved; by decreasing accumulated unobligated balances, an optimum level of resource utilization was to be attained by 1986. Second, procedures for the procurement of goods and services were to be streamlined in order to permit substantial increases in programme delivery. Third, systematic project evaluation was to lead to a number of specific actions that would increase the effectiveness of the Agency's development assistance. With regard to the first aim, implementation increased by 44% over the 1983 level, passing the $30 million mark in October and reaching $36.6 million by the end of the year. Of this amount, $31.8 million related to the implementation of activities programmed for 1984. Therefore, an increase in total resources of only 4% was accompanied by an increase in current-year implementation of 34%. As a result, the upward trend in the unobligated balance was checked, and earmarkings against the TACF actually decreased. The implementation rate against the TACF rose from 58% in 1983 to 65% in 1984, reaching the level that had been set as a target. If this performance can be maintained in 1985, it will be possible to reach the optimum level of TACF resource utilization one year earlier than originally expected. As regards the second aim, streamlined procedures introduced in

  7. 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...

  8. Activity report of Japanese Nuclear Data Committee in period of April 1997 to March 1999

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1997 to March 1999. In this period, preparation of the next version of the Japanese Evaluated Nuclear Data Library, JENDL-3.3, has progressed. Generation of the special purpose files also has been advanced. In this report, the activities of each group affiliated by the committee are presented and the following are described as special topics : (1) progress in evaluating JENDL-3.3, (2) production of JENDL Covariance File and its processing system, (3) completion of the JENDL Dosimetry File, and (4) the JENDL FP Decay Data File. (author)

  9. DOE Technical Standards List. Directory of DOE and contractor personnel involved in non-government standards activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    This is a periodic report on the level of agency participation in non-Government standards activities. This technical standards list is intended to assist US Department of Energy (DOE) management and other personnel involved in the DOE technical Standards Program by identifying those participating individuals. The body of this document contains a listing of DOE employees and DOE contractors who have submitted a Record of Non-Government Standards Activity. Additional names were added from rosters supplied by non-Government standards bodies. Appendices to this document are provided to list the information by parent employment organization, by non-Government standards activity, and by the proper names of the non-Government standards organizations and committees.

  10. 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

  11. Introductory statement to the Technical Assistance and Cooperation Committee of the Board of Governors. 22 November 2004, Vienna, Austria

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2004-01-01

    The Agency's technical cooperation (TC) programme continues to focus on putting advanced science to work to meet the economic and social needs of developing countries. This statement describes TC programme planning and management, including the recent change initiative, highlight a number of key activities, and review the current status of TC funding. The TC programme remains a principal mechanism for expanding the contribution that nuclear technologies make to development. A few areas in which the Agency's efforts are making a difference are: Food and Agriculture; Cancer Radiotherapy and PACT; Positive Influence of Model Projects on Safety and Security of Nuclear Activities; Nuclear Security. The Agency's technical cooperation programme is, at its essence, a network of partnerships - primarily partnerships between the Agency and its Member States, but also including partners from other government institutions, relevant United Nations system agencies, non-governmental organizations, and private sector donors. Working together, an important tool was created for transferring nuclear science and technology to the benefit of developing countries

  12. 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

  13. 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.

  14. Technical Publications as Indicators for Nuclear Fuel Cycle Declarable Activities

    International Nuclear Information System (INIS)

    Schuler, R.; El Gebaly, A.; Feldman, Y.; Gagne, D.; Schot, P.-M.; Ferguson, M.

    2015-01-01

    The Department of Safeguards aims to provide credible assurances to the international community that States are fulfiling their safeguards obligations in that all nuclear material remains in peaceful use. It does so in part by developing and implementing methodologies for early detection of undeclared activities or misuse of nuclear material or technology, based on large and diverse sources of information. Analyzing scientific, technical and patent information allows analysts in the Department to understand the technology available to a State, to forecast possible technical developments, to map collaborative research activities within and across States, and compare that information with declarations received by the State for completeness and correctness. Furthermore, with regard to patent information, scientists or companies want to make sure their intellectual property is protected; accordingly, patents are frequently filed before the information is published elsewhere, making patent information also an early indicator of relevant activities. Dealing with such large information sources requires the use of an innovative methodology conducting analysis. The Department has recently begun to examine the efficacy of link analysis tools to help carry out its mission. Using the link analysis platform Palantir, the authors conducted several case studies with the aim of deriving sound analytical results from large amounts of technical information within a reasonable time frame. The authors used data sets of bibliographic references from the IAEA International Nuclear Information System (INIS),Web of Science, Science Direct and data on worldwide patents from the European Patent Office (EPO). Based on these case studies, the authors are developing methodologies for the efficient application of link analysis to scientific and technical information, thus strengthening the Department's information collection and analysis capabilities and the overall process of State

  15. 75 FR 51525 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

    Science.gov (United States)

    2010-08-20

    .... The Working Group continues to work on after arrival orders, and at the September 25-26, 2008, meeting... protecting persons who work on, under, or between rolling equipment and persons applying, removing or.... 63] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad...

  16. Activity report of Japanese Nuclear Data Committee in the period of April 1977 -- March 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This is a progress report of Japanese Nuclear Data Committee, covering the activities during the period of April 1977 -- March 1979. As special topics, the results of integral tests of Japanese Evaluated Nuclear Data Library, version 1 and the program for version 2 evaluation are described. (author)

  17. 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.

  18. 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

  19. 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

  20. High committee for nuclear safety transparency and information. Annual activity report. June 2008 - December 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This document is the first activity report of the High committee for nuclear safety transparency and information (HCTISN), created on June 18, 2008. The HCTISN is a French authority of information, dialogue and debate about the risks linked with nuclear activities and about their impacts on public health, on the environment and on nuclear safety. The committee has the ability to express his opinion and recommendations about any question on the above topics and to propose any measure aiming at warranting or improving the transparency in the nuclear domain. This activity report offers a synthetic overview of the actions already undertaken: the plutonium imports from UK, the contamination incident at the Socatri facility (a Areva-Eurodif daughter company located at the Tricastin site), and the dismantling strategy of basic nuclear facilities. It presents the composition, organization, missions and means of the Committee, the different working groups and the follow-up of the different recommendations emitted so far by the Committee. (J.S.)

  1. 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.

  2. 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

  3. 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)

  4. 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).

  5. 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)

  6. 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.

  7. The international ISOE programme. ISOE European technical centre activities

    International Nuclear Information System (INIS)

    Ascenzo, L. d'; Crouail, P.; Levy, F.; Livolsi, P.; Schieber, C.; Lefaure, C.

    1996-01-01

    The CEPN has been involved from the beginning in the NEA Information System on Occupational Exposure (ISOE). As ISOE European Technical Centre, the CEPN is responsible for the collection and distribution of European data to the various ISOE partners, the collection of data from the other regional technical centres, and the custodianship of the full ISOE data base. This full data base is updated annually and distributed to all the European participating utilities and to other Regional Technical Centres. The European data are also sent to the European Commission (EC) as a contribution to their own occupational exposure data base. In addition to these activities, the CEPN has developed two computer programmes under Windows to facilitate the management of ISOE data bases. The first software, called ASPIC, allows participating utilities to electronically complete NEA1 and NEA3 questionnaires, as well as to consult the NEA3 data base using key words search routine. This software is available in six different languages. The second programme is a relational data base for the performance of statistical analyses using data from NEA1. The CEPN also contributes significantly to the efficient flow of information through the ISOE Network. This includes participation in the preparation and distribution of the ISOE Annual Report (which presents and analyses NEAI data), ISOE Information Sheets (providing short synthesis using NEA1 and NEA3 data), and Technical Reports. Participating Authorities and Utilities have each made information requests to the CEPN concerning dosimetric data, radiation protection experiences, policies and practices. Some examples of these requests, and of the types of data provided, will be presented. (author)

  8. Committee on Military Nutrition Research Activity Report 1986 - 1992.

    Science.gov (United States)

    1992-06-29

    and to delay gastric emptying. there may be an increased incidence of ’heartburn’ due to reflux esophagitis , which can be debilitating in some people...enteric infection or diarrhea, which could be aggravated by the high-fat ration. C. Since high-fat diets are known to lower esophag al sphincter pressure...with depressed NK activity (Levy et al., 1991 a,b). Gastro -intestinal infections have also caused problems in other Rangar Training classes. However, it

  9. Activities of HPS standards committee in environmental remediation

    International Nuclear Information System (INIS)

    Stencel, J.R.

    1994-01-01

    The Health Physics Society (HPS) develops American National Standards in the area of radiation protection using methods approved by the American National Standards Institute (ANSI). Two of its sections, Environmental Health Physics and Contamination Limits, have ongoing standards development which are important to some environmental remediation efforts. This paper describes the role of the HPS standards process and indicates particular standards under development which will be of interest to the reader. In addition, the authors solicit readers to participate in the voluntary standards process by either joining active working groups (WG) or suggesting appropriate and relevant topics which should be placed into the standards process

  10. 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

  11. 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

  12. Entrustable Professional Activities for Pathology: Recommendations From the College of American Pathologists Graduate Medical Education Committee.

    Science.gov (United States)

    McCloskey, Cindy B; Domen, Ronald E; Conran, Richard M; Hoffman, Robert D; Post, Miriam D; Brissette, Mark D; Gratzinger, Dita A; Raciti, Patricia M; Cohen, David A; Roberts, Cory A; Rojiani, Amyn M; Kong, Christina S; Peterson, Jo Elle G; Johnson, Kristen; Plath, Sue; Powell, Suzanne Zein-Eldin

    2017-01-01

    Competency-based medical education has evolved over the past decades to include the Accreditation Council for Graduate Medical Education Accreditation System of resident evaluation based on the Milestones project. Entrustable professional activities represent another means to determine learner proficiency and evaluate educational outcomes in the workplace and training environment. The objective of this project was to develop entrustable professional activities for pathology graduate medical education encompassing primary anatomic and clinical pathology residency training. The Graduate Medical Education Committee of the College of American Pathologists met over the course of 2 years to identify and define entrustable professional activities for pathology graduate medical education. Nineteen entrustable professional activities were developed, including 7 for anatomic pathology, 4 for clinical pathology, and 8 that apply to both disciplines with 5 of these concerning laboratory management. The content defined for each entrustable professional activity includes the entrustable professional activity title, a description of the knowledge and skills required for competent performance, mapping to relevant Accreditation Council for Graduate Medical Education Milestone subcompetencies, and general assessment methods. Many critical activities that define the practice of pathology fit well within the entrustable professional activity model. The entrustable professional activities outlined by the Graduate Medical Education Committee are meant to provide an initial framework for the development of entrustable professional activity-related assessment and curricular tools for pathology residency training.

  13. Future strategies on IAEA activities and technical cooperation programmes

    International Nuclear Information System (INIS)

    Kim, Kyoung Pyo; Hong, Young Don

    1998-10-01

    This study provides basic background information about the establishment of the IAEA, its mission, major activities, General Conference , and Board of Governors, structure and functions of the Secretariat. The IAEA Mid-term plan, to be implemented in the years 1998 - 2003, includes the enhancement of its functional effectiveness, analysis of the changing developments, adjustment of its priorities, and evaluation of its programmes, are describes in full detail. This plan is divided into 6 major areas ; nuclear power and the fuel cycle, nuclear applications, nuclear, radiation and radwaste safety, verification and security of nuclear material, management of technical cooperation for development, policy making, coordination and support. It is also expected that the IAEA plan provides an opportunity to understand the future directions of IAEA programmes and its operational philosophy, thus greatly contributing to Koreas establishment of its own future directions for expanded cooperation with the IAEA, and urges to device effective domestic strategies. This plan will also contribute to the evaluation of Koreas responsibility as a member of the Board of Governors as well as enhance Koreas role as an Advisory Group Member. It is expected that this study is useful for nuclear-related organizations wishing to establish basic directions for the efficient implementation of IAEA technical cooperation programs in the future. (author). 16 refs., 6 tabs., 16 figs

  14. Report of Committee for JAEA Internationalization Initiative. Focusing on the activities of local teams

    International Nuclear Information System (INIS)

    2015-10-01

    The 'Committee for JAEA Internationalization Initiative' was established in 2010 with the view to discuss the policy and improvement plans for JAEA's achievement of an international center of excellence (ICOE), which include improving the environment to accept foreign researchers, etc. The existing issues to be solved in the effort for ICOE and recommendations for the solutions, which were discussed in the committee, and challenges in developing human resources with a global mindset were written in the report summarizing the activities conducted in the following two years. This report was compiled focusing on the efforts in respective sites made during a period of two years from 2013 to 2014 by the local teams that were set up in accordance with the situation of the R and D centers hosting a number of foreign researchers, etc. based on the above-mentioned recommendations. (author)

  15. General activities of JAERI nuclear data center and Japanese nuclear data committee

    International Nuclear Information System (INIS)

    Fukahori, Tokio

    1999-01-01

    The nuclear data center of Japan Atomic Energy Research Institute (JAERI/NDC) is playing the role of Japanese domestic nuclear data center and gateway to foreign data centers. As the domestic nuclear data center, activities of JAERI/NDC are 1) compiling the Japanese Evaluated Nuclear Data Library (JENDL) for both general and special purposes, 2) importing and exporting nuclear data, 3) nuclear data services for the domestic users, and 4) organizing japanese Nuclear Data Committee (JNDC) as a secretariat. Compiled JENDL General Purpose Files up to now are JENDL-1, 2, 3, 3.1 and 3.2. The data for 340 nuclei in the energy range from 10 -5 eV to 20 MeV are available in JENDL-3.2. JENDL Special Purpose Files were also prepared in order to meet the requests from the specified application fields. JNDC has about 140 members. JNDC consists of Main Committee, Steering Committee, Subcommittee on Nuclear Data, Subcommittee on Reactor Constants, Subcommittee on Nuclear Fuel Cycle and Standing Groups. Above subcommittees are performing essential evaluation for the files described above, checking the JENDL files through the benchmark and integral testing as well as considering the standard group constant, and considering about evaluation of decay heat and nuclide generation/depletion and fission product yields. (author)

  16. 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.

  17. 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

  18. 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.

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

    International Nuclear Information System (INIS)

    1995-07-01

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

  20. 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.

  1. 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

  2. The Consolidated Human Activity Database — Master Version (CHAD-Master) Technical Memorandum

    Science.gov (United States)

    This technical memorandum contains information about the Consolidated Human Activity Database -- Master version, including CHAD contents, inventory of variables: Questionnaire files and Event files, CHAD codes, and references.

  3. Activity report of Japanese Nuclear Data Committee in period of April 1993 to March 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This is a progress report on the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1993 to March 1995. In this period, the latest version of the Japanese Evaluated Nuclear Data Library, JENDL-3.2, has been released for users after benchmark tests of data therein. Preparation of the special purpose nuclear data files has been also progressed. As special topics, the followings are presented here : (1) the completion and benchmark tests of the JENDL-3.2, (2) progress in evaluating special purpose nuclear data, (3) progress in studying high energy nuclear data, and (4) utilization of nuclear data by means of internet. (author)

  4. Committee for nuclear safety information and transparency. Activity annual report, June 2008 - December 2009

    International Nuclear Information System (INIS)

    2010-01-01

    After a presentation of the composition, organisation, missions and means of this institution, this report presents the main domain of activity (the transport of plutonium, the SOCATRI incident and submission to the State minister, the nuclear installation dismantling strategy), and the three working groups (transparency and secrets, Internet portal, environment radioactivity index). It reports the taking into account of recommendations previously expressed by the committee (about import and transport of plutonium between Great-Britain and France, about information of population and patients on radiological and nuclear medicine events)

  5. Activity report of Japanese Nuclear Data Committee in period of April 1983 to March 1985

    International Nuclear Information System (INIS)

    1985-01-01

    This is a progress report on the activities of the Japanese Nuclear Data Committee (JNDC) in the period of April 1983 to March 1985. Special topics are presented on improvements of the nuclear data evaluation methodology, on the study of nuclear model parameters, and on a development of the cross section sensitivity and adjustment code system. Application of the nuclear data to new fields such as fuel cycle and to medical science is also reported. Moreover, some tasks to promote the distribution and utilization of the Japanese Evaluated Nuclear Data Library (JENDL) are described. (author)

  6. Nuclear Safety Research Review Committee

    International Nuclear Information System (INIS)

    Todreas, N.E.

    1990-01-01

    The Nuclear Safety Research Review Committee has had a fundamental difficulty because of the atmosphere that has existed since it was created. It came into existence at a time of decreasing budgets. For any Committee the easiest thing is to tell the Director what additional to do. That does not really help him a lot in this atmosphere of reduced budgets which he reviewed for you on Monday. Concurrently the research arm of Nuclear Regulatory Commission has recognized that the scope of its activity needed to be increased rather than decreased. In the last two-and-a-half-year period, human factors work was reinstated, radiation and health effects investigations were reinvigorated, research in the waste area was given significant acceleration. Further, accident management came into being, and the NRC finally got back into the TMI-2 area. So with all of those activities being added to the program at the same time that the research budget was going down, the situation has become very strained. What that leads to regarding Committee membership is a need for technically competent generalists who will be able to sit as the Division Directors come in, as the contractors come in, and sort the wheat from the chaff. The Committee needs people who are interested in and have a broad perspective on what regulatory needs are and specifically how safety research activities can contribute to them. The author summarizes the history of the Committee, the current status, and plans for the future

  7. CEA technical-economic activity report - Year 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This report presents an assessment of activities undertaken by the CEA in the field of energy technique and economy during 2014. Technical-economic studies aims at contributing to national orientations on energy, at R and D program orientations, at highlighting and strengthening synergies between nuclear technologies and new energy technologies, and at strengthening the credibility of these technologies. After a presentation of the organisation of technique and economy within the CEA, of the involved bodies and departments, of the addressed themes (photovoltaic, wind, biomass and biofuels, hydrogen-based systems, mobility, electric systems and grids), the report presents studies performed in relationship with the national energy strategy and with energy scenarios, studies performed in the nuclear field (on fourth-generation reactors, on the front-end and back-end of the fuel cycle), studies performed in the field of new energy technologies and climate (hydrogen and storage, biofuels, climate, mobility, solar, electric systems). The next part addresses academic aspects, methodological studies and modelling studies. Contributions and participations to conferences, and publications are indicated

  8. Technical and economic impacts of active management on distribution network

    International Nuclear Information System (INIS)

    Zhang, Jietan; Cheng, Haozhong; Wang, Chun

    2009-01-01

    With the deregulation of energy market and the appeal for environment protection, more and more distributed generation (DG) is embedded in the distribution network. However the approach of connecting DG in most cases is based on a so-called ''fit and forget'' policy and the capacity of DG is limited rigidly by distribution network operator (DNO) to avoid the negative effects of high level penetration. Therefore active management (AM) is put forward as an effective method to network reinforcement for the connection and operation of DG. In this paper, the concept and principle of AM are introduced, and several indices are proposed to evaluate both technical and economic impacts of AM on distribution network with DG. To simplify the simulation fuzzy C-means clustering (FCM) algorithm is introduced. The test results on a sample system represent that AM will lead to decrease of power generation of DG, but it can reduce energy losses and improve voltage profile effectively. Furthermore, AM will take great economic incentives to DG developer as well as DNO with reasonable policy. (author)

  9. 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

  10. 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.

  11. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    2002-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

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

  15. 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

  16. 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.

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

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this Tcm are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. Today the nuclear industry relies much more on existing facilities than on the design of new ones. Nevertheless it appears that safety evaluation against external hazards is not a decreasing activity. The reason being that maintaining an acceptable level of nuclear safety requires periodic re-assessments of facilities, either because of modifications of the environment due to human activity or because of new data or new approaches in the assessment of natural hazards. In this regard, seismic re-evaluation has increasingly become a key issue for several existing nuclear facilities, including not only nuclear power plants but also other plants of the fuel cycle, as well as research reactors or laboratories. The IAEA has already supported development of engineering practices in this field by managing a Co-ordinated Research Programme, launched in 1992, on a Benchmark Study for the seismic analysis and testing of WWER 1000 type NPPs. It is now proposed to investigate other aspects of this issue. Many of these facilities were built according to older standards which did not take into account seismic hazard. Consequently, the seismic re-evaluation of existing facilities is a real challenge for earthquake engineers. In most of the cases, it is impossible to re-evaluate according to the up to date standards because entering these standards implies that some design rules are met, what is generally not the case for older facilities. In the best cases some rules exist for non nuclear buildings. In order to achieve a consensus on this matter, the IAEA intends to edit a Safety Report on 'Seismic Evaluation of existing NPPs'. The TCM will offer the opportunity to review the draft of

  18. Recreational technical diving part 1: an introduction to technical diving methods and activities.

    Science.gov (United States)

    Mitchell, Simon J; Doolette, David J

    2013-06-01

    Technical divers use gases other than air and advanced equipment configurations to conduct dives that are deeper and/or longer than typical recreational air dives. The use of oxygen-nitrogen (nitrox) mixes with oxygen fractions higher than air results in longer no-decompression limits for shallow diving, and faster decompression from deeper dives. For depths beyond the air-diving range, technical divers mix helium, a light non-narcotic gas, with nitrogen and oxygen to produce 'trimix'. These blends are tailored to the depth of intended use with a fraction of oxygen calculated to produce an inspired oxygen partial pressure unlikely to cause cerebral oxygen toxicity and a nitrogen fraction calculated to produce a tolerable degree of nitrogen narcosis. A typical deep technical dive will involve the use of trimix at the target depth with changes to gases containing more oxygen and less inert gas during the decompression. Open-circuit scuba may be used to carry and utilise such gases, but this is very wasteful of expensive helium. There is increasing use of closed-circuit 'rebreather' devices. These recycle expired gas and potentially limit gas consumption to a small amount of inert gas to maintain the volume of the breathing circuit during descent and the amount of oxygen metabolised by the diver. This paper reviews the basic approach to planning and execution of dives using these methods to better inform physicians of the physical demands and risks.

  19. 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...

  20. TU-G-213-01: IEC and US Committee Activities and Organizational Structure

    Energy Technology Data Exchange (ETDEWEB)

    Ibbott, G. [UT MD Anderson Cancer Center (United States)

    2015-06-15

    The International Electrotechnical Commission (IEC) writes standards that manufacturers of electrical equipment must comply with. Medical electrical equipment, such as medical imaging, radiation therapy, and radiation dosimetry devices, fall under Technical Committee 62. Of particular interest to medical physicists are the standards developed within Subcommittees (SC) 62B, which addresses diagnostic radiological imaging equipment, and 62C, which addresses equipment for radiation therapy, nuclear medicine and dosimetry. For example, a Working Group of SC 62B is responsible for safety and quality assurance standards for CT scanners and a Working Group of SC 62C is responsible for standards that set requirements for dosimetric safety and accuracy of linacs and proton accelerators. IEC standards thus have an impact on every aspect of a medical physicist’s job, including equipment testing, shielding design, room layout, and workflow. Consequently, it is imperative that US medical physicists know about existing standards, as well as have input on those under development or undergoing revision. The structure of the IEC and current standards development work will be described in detail. The presentation will explain how US medical physicists can learn about IEC standards and contribute to their development. Learning Objectives: Learn about the structure of the IEC and the influence that IEC standards have on the design of equipment for radiology and radiation therapy. Learn about the mechanisms by which the US participates in the development and revision of standards. Understand the specific requirements of several standards having direct relevance to diagnostic and radiation therapy physicists.

  1. Activities of the O ampersand M committee history ampersand future perspectives

    International Nuclear Information System (INIS)

    Poulis, D.S.

    1996-01-01

    This paper gives an overview of the Committee on Operation and Maintenance of Nuclear Power Plants, hereafter referred to as the O ampersand M Committee, formed in June 1975 when the American National Standard Institute's Committee on Reactor Plants and their Maintenance was disbanded. The O ampersand M Committee's history, structure, current focus and future perspectives will be presented. The purpose of this paper is to give information to industry and the public of the Committee's on-going effort to make accurate and timely responses to the needs of the nuclear industry

  2. Report of Activity, 1996 - 1997. Vol. 3. General activities - Technical Research

    International Nuclear Information System (INIS)

    Pouthas, Joel; Hutin, Christiane; Niogret Mathias

    1999-01-01

    This is the third tome of the Report of Activity of IPN - Orsay on 1996-1997. It deals with general activities and technical research. Summary reports and short communications are grouped in the following sections: 1 - Accelerators with the sub-divisions 1.1 - R and D on superconducting RF cavities; 1.2 - SPIRAL Project; 1.3 - Contribution to the LHC Project; 1.4 - Tandem; 2 - Targets, Sources and Injectors; 3 - Detectors and related instrumentation; 4 - Electronics; 5 - Data processing; 6 - Radioprotection and medical applications

  3. 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

  4. Technical possibility of the practice of the 1976 regulation: comment on the reply of the special committee

    Energy Technology Data Exchange (ETDEWEB)

    Nishimura, H

    1975-01-01

    The 1976 Japanese regulations for automobile exhaust are reviewed. Topics include: The meaning of the 1976 regulations, a comparison with those in the United States, problems with the regulations, the present status of technical developments to achieve the regulations, problems related to stratified charge engines, and attitudes and techniques of the big car makers. In an appendix, information on the Kumagaya engines, fuel consumption of various engines, and problems of vibration are presented. The main purpose of the 1976 regulations is to decrease the amount of nitrogen oxides in the exhaust gas to 0.25 g/km. The average carbon monoxide, hydrocarbon, and NOx levels for the Honda stratified charge engines are 1.4, 0.125, and 0.5 g/km. It is possible to reduce this content further. However, the driving characteristics of the cars deteriorate rapidly at lower NOx levels. According to the opinions of Toyota and Nissan, the two largest car makers in Japan, the practical NOx content is 1.0 to 1.1 g/kg from the standpoint of the technological level of the Japanese car industry in 1976.

  5. Drug and therapeutics committees in Danish hospitals: a survey of organization, activities and drug selection procedures

    DEFF Research Database (Denmark)

    Plet, H. T.; Hallas, J.; Nielsen, Gitte S.

    2013-01-01

    To implement rational pharmacotherapy in hospitals, it is important to develop, implement and evaluate hospital drug formularies (HDFs). A report from Denmark recommended standardizing activities of the drug and therapeutics committees (DTCs) in Denmark, but little is known about their current...... organization. The aim of the study was to describe the organization of DTCs in Denmark, how HDFs are developed and implemented, and to what extent policies that support the use of HDFs exist. A questionnaire was developed based on previous research and guidelines and contained 20 questions, which were divided...... of the meetings lasted between 1 and 2.5 hr. Eight (89%) DTCs developed HDFs, policies and guidelines (P&Gs) that supported the use of HDFs. Eight (89%) had established criteria for inclusion of drugs on the HDFs, and seven had developed criteria for generic substitution and therapeutic interchange. The number...

  6. Report of International NanoSPD Steering Committee and statistics on recent NanoSPD activities

    International Nuclear Information System (INIS)

    Valiev, R Z; Langdon, T G

    2014-01-01

    Abstract. The Université de Lorraine in Metz, France, is the selected site for the 6th International Conference on Nanomaterials by Severe Plastic Deformation (NanoSPD6) following a series of five earlier conferences. This introductory paper reports on several major developments in NanoSPD activities as well as on very recent NanoSPD citation data which confirm the continued growth and expansion of this important research area. Close attention is given to the topics of workshops, conferences and seminars organized during these last three years as well as on books and reviews published prior to the NanoSPD6 conference. A special concern of the committee is in introducing and discussing the appropriate terminology to be applied in this new field of materials science and engineering

  7. Technical committee on review of national programmes on fast reactors and accelerator driven systems (ADS). Working material

    International Nuclear Information System (INIS)

    2001-01-01

    The objectives of the meeting were: to exchange information on the national programmes on fast reactors (FR) and accelerator driven systems (ADS); to review the progress since the previous IWG-FR meeting, including the status of the actions; to consider meeting arrangements for 2001 and 2002; to review the Agency co-ordinated research activities in the field of FR and ADS, as well as so-ordination of the TWG-FR activities with their organisations. This report covers the reports presented on the relevant activities in Brazil, China, France, Germany, India, Italy, Japan, Kazakhstan, Republic of Korea, Russia, Sweden, United Kingdom and USA

  8. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

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

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

    International Nuclear Information System (INIS)

    1995-03-01

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

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

    International Nuclear Information System (INIS)

    1995-10-01

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

  12. 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.

  13. 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

  14. Integrating public information activities on a technical project

    International Nuclear Information System (INIS)

    Little, Sh. K.; Vecchiola, S.F.

    1984-01-01

    Through gradual evolution and successful performance, the WIPP Communications group has gained respect and recognition as a dual service organization that offers numerous benefits to a technical project. Westinghouse assembled a team that has successfully coordinated and encouraged an exchange of information not only with the public information realm but also as a project service and function. WIPP has combined educational services, external and employee communication and public information into one unit called ''Communications''

  15. Promoting proteomics knowledge in Europe: report on the activities of the EuPA Education Committee 2006-2007

    DEFF Research Database (Denmark)

    Albar, Juan Pablo; Corthals, Garry L; Gil, Concha

    2007-01-01

    the last year the EuPA Education Committee has coordinated or supported different educational activities including basic and advanced courses, a summer school, workshops and tutorials. A new programme of basic courses dubbed "Teaching the Teachers" has been initiated. These courses reach a larger, Europe...

  16. The National Shipbuilding Research Program, Proceedings of the REAPS Technical Symposium Paper No. 1: Ship Production Committee Panel Overviews

    Science.gov (United States)

    1980-10-01

    Reports, 1215 Jefferson Davis Highway, Suite 1204, Arlington VA 22202-4302. Respondents should be aware that notwithstanding any other provision of law ...25 (4). April. 9. Vaughn and Allen, "The Development of Production Control in Ship- building", Kongsberg Japan Fabrils , Shipbuilding Symposium. Con...consistent with the law . • Participate in activities of voluntary standards bodies when such is in the public interest. • Coordinate agency

  17. Annual activities report of Brazilian Aerospace Technical Center -CTA/IEAv - 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This document reports the research activities on nuclear physics and reactors physics and engineering in the Brazilian Aerospace Technical Center/Advanced Studies Institute, Sao Paulo State, in the year of 1989

  18. Seismic evaluation of existing nuclear power plants and other facilities V. 2. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this TCM are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. This volume includes presentations of the member states describing the practical approach to evaluation of seismic equipment of the existing NPPs, validation of innovative systems for earthquake protection; seismic re-evaluation of the NPPs, seismic regulations and safety standards; and other activities related to seismic safety in Member States

  19. Seismic evaluation of existing nuclear power plants and other facilities V. 2. Proceedings of the technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    The objectives of this TCM are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. This volume includes presentations of the member states describing the practical approach to evaluation of seismic equipment of the existing NPPs, validation of innovative systems for earthquake protection; seismic re-evaluation of the NPPs, seismic regulations and safety standards; and other activities related to seismic safety in Member States.

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

    Energy Technology Data Exchange (ETDEWEB)

    Janev, R K

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-01

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

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

    International Nuclear Information System (INIS)

    Janev, R.K.

    1999-05-01

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

  3. Design and development of gas cooled reactors with closed cycle gas turbines. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Technological advances over the past fifteen years in the design of turbomachinery, recuperators and magnetic bearings provide the potential for a quantum improvement in nuclear power generation economics through the use of the HTGR with a closed cycle gas turbine. Enhanced international co-operation among national gas cooled reactor programmes in these common technology areas could facilitate the development of this nuclear power concept thereby achieving safety, environmental and economic benefits with overall reduced development costs. This TCM and Workshop was convened to provide the opportunity to review and examine the status of design activities and technology development in national HTGR programmes with specific emphasis on the closed cycle gas turbine, and to identify pathways which take advantage of the opportunity for international co-operation in the development of this concept. Refs, figs, tabs.

  4. Design and development of gas cooled reactors with closed cycle gas turbines. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-08-01

    Technological advances over the past fifteen years in the design of turbomachinery, recuperators and magnetic bearings provide the potential for a quantum improvement in nuclear power generation economics through the use of the HTGR with a closed cycle gas turbine. Enhanced international co-operation among national gas cooled reactor programmes in these common technology areas could facilitate the development of this nuclear power concept thereby achieving safety, environmental and economic benefits with overall reduced development costs. This TCM and Workshop was convened to provide the opportunity to review and examine the status of design activities and technology development in national HTGR programmes with specific emphasis on the closed cycle gas turbine, and to identify pathways which take advantage of the opportunity for international co-operation in the development of this concept. Refs, figs, tabs

  5. Impact of the economic crisis on the activity of a clinical research ethics committee

    Directory of Open Access Journals (Sweden)

    Paula Arcenillas

    2014-11-01

    Full Text Available Purpose: Analyze the impact of economic and social crisis in volume and funding of clinical trials (CT and observational studies (ES from the activity of an Research Ethics Committee (REC. Method: REC memories 2003-2012 were reviewed. Financing of evaluated projects, CT and OS were analyzed classifying them into four groups: 1 promoted by pharmaceutical industry, 2 by scientific societies with industry support, 3 by scientific societies with government support and 4 unfunding.Two periods were compared: pre-crisis (2003-2007 and crisis (2008-2012. Results: During 10 studied years, 744 protocols were evaluated: a 71% of group 1, a 9% of group 2, a 3% of group 3 and a 17% was no funding. Regarding OS, 40%, 5,4%, 8,6% and 46% were the groups 1, 2, 3 and 4 respectively. Analyzing crisis versus pre-crisis period, statistically significant differences were observed in the decreasing of number of CT phase 2 and 3 and in the rising EO. Comparing crisis related to the pre-crisis period, the Group 4 increased statistically significantly. Conclusions: Evolution of total number of studies evaluated by REC tends to be maintained and even increased over time. REC maintains its activity and even increased at the expense of financing and unfunded OS.

  6. [Impact of the economic crisis on the activity of a clinical research ethics committee].

    Science.gov (United States)

    Redondo Capafons, S; Arcenillas, Paula; Giménez, Nuria; March López, Pablo; Soriano, Laura; Pla, Ramon; Quintana, Salvador

    2014-11-03

    Analyze the impact of economic and social crisis in volume and funding of clinical trials (CT) and observational studies (ES) from the activity of an Research Ethics Committee (REC). REC memories 2003-2012 were reviewed. Financing of evaluated projects, CT and OS were analyzed classifying them into four groups: 1) promoted by pharmaceutical industry, 2) by scientific societies with industry support, 3) by scientific societies with government support and 4) unfunding.Two periods were compared: pre-crisis (2003-2007) and crisis (2008-2012). During 10 studied years, 744 protocols were evaluated: a 71% of group 1, a 9% of group 2, a 3% of group 3 and a 17% was no funding. Regarding OS, 40%, 5,4%, 8,6% and 46% were the groups 1, 2, 3 and 4 respectively. Analyzing crisis versus pre-crisis period, statistically significant differences were observed in the decreasing of number of CT phase 2 and 3 and in the rising EO. Comparing crisis related to the pre-crisis period, the Group 4 increased statistically significantly. Evolution of total number of studies evaluated by REC tends to be maintained and even increased over time. REC maintains its activity and even increased at the expense of financing and unfunded OS. Copyright AULA MEDICA EDICIONES 2014. Published by AULA MEDICA. All rights reserved.

  7. 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)

  8. 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)

  9. Joint Integration Office Independent Review Committee annual report, 1985

    International Nuclear Information System (INIS)

    1986-08-01

    Comprised of seven persons with extensive experience in the issues of nuclear waste, the Independent Review Committee (IRC) provides independent and objective review of Defense Transuranic Waste Program (DTWP) activities managed by the Joint Integration Office (JIO), formerly the Defense Transuranic Waste Lead Organization (TLO). The Committee is ensured a broad, interdisciplinary perspective since its membership includes representatives from the fields of nuclear engineering, nuclear waste transportation, industrial quality control, systems and environmental engineering and state and local government. The scope of IRC activities includes overall review of specific TLO plans, projects and activities, and technical review of particular research and development projects. The Committee makes specific suggestions and recommendations based upon expertise in the field of TRU Waste Management. The IRC operates as a consulting group, under an independent charter providing objective review of program activities. This report summarizes the 12 major topics reviewed by the committee during 1985

  10. Technical activity profile and influence of body anthropometry on playing performance in female elite team handball

    DEFF Research Database (Denmark)

    Michalsik, Lars B; Aagaard, Per; Madsen, Klavs

    2015-01-01

    regular tournament match seasons. Technical match activities were distributed in 6 major types of playing actions (shots, breakthroughs, fast breaks, technical errors, defensive errors, and tackles) and further divided into various subcategories (e.g., type of shot, hard or light tackles, claspings......, screenings, and blockings). Furthermore, anthropometric measurements were performed. Each player had 28.3 ± 11.0 (group means ± SD) high-intense playing actions per match with a total effective playing time of 50.70 ± 5.83 minutes. On average, each player made 2.8 ± 2.6 fast breaks, gave 7.9 ± 14...... that female elite TH players during competitive games intermittently perform a high number of short-term, high-intense technical playing actions making modern female elite TH a physically demanding team sport. No sign of technical fatigue were observed, since the amount of intense technical playing actions...

  11. 100 Areas technical activities report -- Physics, October 1949

    Energy Technology Data Exchange (ETDEWEB)

    Gast, P.F.

    1949-11-21

    This report contains brief summaries of activities at the Hanford production reactors for the month of Oct. The activities for the Pile Physics Group are: (1) H Area start-up; (2) outlet temperature recording systems; (3) reactivity balance for each pile for this period. Activities for the Experimental Physics Group are: (1) graphite testing; (2) 305 testing -- P-slug standardization and graphite standards; (3) shielding. Also status is given on critical mass project.

  12. 78 FR 56871 - Advanced Scientific Computing Advisory Committee

    Science.gov (United States)

    2013-09-16

    ... Germantown Update on Exascale Update from Exascale technical approaches subcommittee Facilities update Report from Applied Math Committee of Visitors Exascale technical talks Public Comment (10-minute rule) Public...

  13. Application of the Commission’s recommendations: the activities of ICRP Committee 4

    International Nuclear Information System (INIS)

    Lochard, Jacques

    2012-01-01

    Committee 4 of the International Commission on Radiological Protection (ICRP) is responsible for developing principles, recommendations, and guidance on the protection of man against radiation exposure; and considering their practical application in all exposure situations. The Committee also acts as a major point of contact between ICRP and other international organisations and professional bodies concerned with protection against ionising radiation. The current work of the Committee involves the development of a series of reports on implementation of the 2007 Recommendations, and a reflection on the ethical foundations of the radiological protection system. Following the accident in Fukushima, Committee 4 also initiated an analysis of management of the consequences of the accident, with the objective of revising, if necessary, the Commission’s publications on emergency and post-accident situations.

  14. IAEA CRP on Fission Yield Data and activity of WG in Japanese Nuclear Data Committee

    International Nuclear Information System (INIS)

    Katakura, Junichi; Fukahori, Tokio

    1999-01-01

    The outline of the coordinate research program on fission yield data organized by International Atomic Energy Agency and the working group on the subject newly organized in Japanese Nuclear Data Committee are presented. (author)

  15. Activity measurements in the Federal Physico-Technical Institute (PTB)

    International Nuclear Information System (INIS)

    Janssen, H.

    1992-01-01

    Absolute methods of activity determination and secondary measuring procedures, which are carried out using ionisation chambers for radioactive solutions and NaI(Tl) detectors as well as extended surface proportional counters for solid substances, are the metrological techniques generally available for measurements of radioactivity. The range of methods discussed here was limited to those that are used most frequently in the routine of activity determinations or directly relevant to nuclear medicine or radiation protection. (orig./DG) [de

  16. Activities of technical cooperation in the countries of Latin America: the case of Costa Rica

    International Nuclear Information System (INIS)

    Solis Diaz, L.

    1998-01-01

    The activities of technical cooperation in the region of Latin America, have been promoted by the own countries, and by the International Atomic Energy Agency, since 1957. In Costa Rica from 1969, the Commission of Atomic Energy of Costa Rica, has developed an intense work in the promotion of the pacific uses of nuclear energy, as well as, the coordination and canalization of the international technical cooperation, toward the national executing institutions. (author) [es

  17. Results of the activities of the Scientific and Technical Coordination Council for Radiation Technique and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Sille, A K [Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj Ehnergii SSSR, Moscow

    1977-03-01

    It is reported on the activities of the Scientific and Technical Coordination Council for Radiation Technique and Technology (STCC-RTT) of the CMEA Permanent Commission for the Peaceful Uses of Atomic Energy according to the programme 1971 to 1975. The STCC-RTT is concerned with technical applications such as radiation sterilization, food irradiation, radiation-induced chemical processes etc. The main tasks which have to be solved within the period from 1976 to 1980 are outlined.

  18. Second meeting of the ITER Preparatory Committee

    International Nuclear Information System (INIS)

    Drew, M.

    2003-01-01

    The committee charged to oversee the ITER ITA (ITER transitional arrangements) the ITER preparatory committee, held its second meeting on 24 September at the JET facilities at Culham, UK. Dr. Umberto Finzi of the European Commission was chairman. This meeting was also the first since the succession by Dr. Yasuo Shimomura to Dr. Robert Aymar as Interim Project Leader (IPL). Welcoming Dr. Shimomura in his new capacity, the Committee paid tribute to the outstanding contributions of his predecessor to the definition, design and promotion of ITER, and expressed the gratitude of all Participants to Dr. Aymar and its best wishes for future success in his new appointment.The technical activities of the ITA were the main focus of the Committee's discussions. The Committee took note of the IPL's Status Report on ITA Technical Activities and endorsed the IPL's proposals for the top level structure of the International Team, including the designation of Dr. Pietro Barabaschi as Deputy to the IPL. The Committee took note of the IPL's proposals on Participants' contributions to the ITA and of the Participants' stated intentions and expectations in this regard. Several Delegations pointed out that access to necessary resources would depend strongly on progress made towards the Agreement. All Participants were invited, in the shared interests of the project, to respond constructively to the specific technical areas where the IPL reported a lack of resources. Following a presentation from the IT on Project Management Tools, the Committee expressed support, in general, for the proposed strategy designed to provide the current team with the CAD and Data Management elements necessary to prepare for an efficient start of ITER construction, and asked the IT Leader to report on an estimate and time profile of expenditure during the period to mid-2004. The Committee supported the proposals to re-establish the ITER Test Blanket Working. The Committee agreed that the phasing of planned

  19. Activities of Institute of Radiation Protection and Dosimety/Brazil as Technical and Scientific Support Organization on Occupational Radiation Protection

    International Nuclear Information System (INIS)

    Da Silva, F.C.A.; Ferreira, P.R.; Matta, L.E.C.; Peres, M.A.L.; Godoy, J.M.; Alencar, M.A.V.; Carlos, M.T.; Souza-Santos, D.; Leocadio, J.C.; Oliveira, M.S.

    2010-01-01

    There are, in Brazil, about 126,000 workers registered on National Dose Registry System (SRD/IRD) as occupationally exposed. They work on 4,000 radioactive installations, 20 nuclear fuel cycle installations and with 90,000 x-ray diagnostic devices. There are two main Regulatory Authorities to license and control these installations on nuclear and radioactive areas, and another Regulatory Authority that is responsible for safety and health protection of workers on their labour activities. Belonging to structure of the National Commission of Nuclear Energy (CNEN-Brazil) there is an Institute dedicated to radiation protection, dosimetry and metrology of ionizing radiation, that is the Institute of Radiation Protection and Dosimetry (IRD). This paper presents two main IRD activities related to occupational radiation protection that can be seen as example of technical and scientific support to Regulatory Authorities: the Radiation Overexposure Analysis that is performed by the Radiation Overexposure Analysis Group (GADE) and the Approval of Individual Monitoring Services and Calibration Laboratory of Equipment used in Radiation Protection that is performed by the Committee for the Evaluation of Essay and Calibration Services (CASEC). (author)

  20. French butane propane committee. 2004 activity report; Comite francais du butane et du propane. Rapport d'activite 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This activity report presents the French butane-propane committee (CFBP), an association for the promotion of liquefied petroleum gases (LPG), the characteristics of LPG fuels, the LPG market and its evolution, the CFBP's missions and the 2004 highlights: representation of subscribing companies, participation to standardization works, making techniques and regulations change, improving the safety of equipments and installations, training and information, promoting LPG products. (J.S.)

  1. French butane propane committee. 2003 activity report; Comite francais du butane et du propane. Rapport d'activite 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This activity report presents the French butane-propane committee (CFBP), an association for the promotion of liquefied petroleum gases (LPG), the characteristics of LPG fuels, the LPG market and its evolution, the CFBP's missions and the 2003 highlights: representation of subscribing companies, participation to standardization works, making techniques and regulations change, improving the safety of equipments and installations, training and information, promoting LPG products. (J.S.)

  2. Active sites in char gasification: Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Wojtowicz, M.; Lilly, W.D.; Perkins, M.T.; Hradil, G.; Calo, J.M.; Suuberg, E.M.

    1987-09-01

    Among the key variables in the design of gasifiers and combustors is the reactivity of the chars which must be gasified or combusted. Significant loss of unburned char is unacceptable in virtually any process; the provision of sufficient residence time for complete conversion is essential. A very wide range of reactivities are observed, depending upon the nature of the char in a process. The current work focuses on furthering the understanding of gasification reactivities of chars. It has been well established that the reactivity of char to gasification generally depends upon three principal factors: (1) the concentration of ''active sites'' in the char; (2) mass transfer within the char; and (3) the type and concentration of catalytic impurities in the char. The present study primarily addresses the first factor. The subject of this research is the origin, nature, and fate of active sites in chars derived from parent hydrocarbons with coal-like structure. The nature and number of the active sites and their reactivity towards oxygen are examined in ''model'' chars derived from phenol-formaldehyde type resins. How the active sites are lost by the process of thermal annealing during heat treatment of chars are studied, and actual rate for the annealing process is derived. Since intrinsic char reactivities are of primary interest in the present study, a fair amount of attention was given to the model char synthesis and handling so that the effect of catalytic impurities and oxygen-containing functional groups in the chemical structure of the material were minimized, if not completely eliminated. The project would not be considered complete without comparing characteristic features of synthetic chars with kinetic behavior exhibited by natural chars, including coal chars.

  3. Legal and technical analysis of the activities involving radiation applications

    International Nuclear Information System (INIS)

    Borges, J.C.

    1991-01-01

    Activities related to radiation applications have been worldwide target of studies concerning biology, medicine, sociology, psychology and law, since prediction of the possible risks and harms associated with the use of radiation, depends on probabilities not easy to quantify, mainly in the most common low-dose situations. In Brazil, legislation generated in the last forty years did not match evolution of the scientific domains related above. This way, more recent rules not rarely conflict with older regulations, without revoking them. (author)

  4. Committee-Based Active Learning for Surrogate-Assisted Particle Swarm Optimization of Expensive Problems.

    Science.gov (United States)

    Wang, Handing; Jin, Yaochu; Doherty, John

    2017-09-01

    Function evaluations (FEs) of many real-world optimization problems are time or resource consuming, posing a serious challenge to the application of evolutionary algorithms (EAs) to solve these problems. To address this challenge, the research on surrogate-assisted EAs has attracted increasing attention from both academia and industry over the past decades. However, most existing surrogate-assisted EAs (SAEAs) either still require thousands of expensive FEs to obtain acceptable solutions, or are only applied to very low-dimensional problems. In this paper, a novel surrogate-assisted particle swarm optimization (PSO) inspired from committee-based active learning (CAL) is proposed. In the proposed algorithm, a global model management strategy inspired from CAL is developed, which searches for the best and most uncertain solutions according to a surrogate ensemble using a PSO algorithm and evaluates these solutions using the expensive objective function. In addition, a local surrogate model is built around the best solution obtained so far. Then, a PSO algorithm searches on the local surrogate to find its optimum and evaluates it. The evolutionary search using the global model management strategy switches to the local search once no further improvement can be observed, and vice versa. This iterative search process continues until the computational budget is exhausted. Experimental results comparing the proposed algorithm with a few state-of-the-art SAEAs on both benchmark problems up to 30 decision variables as well as an airfoil design problem demonstrate that the proposed algorithm is able to achieve better or competitive solutions with a limited budget of hundreds of exact FEs.

  5. 76 FR 19176 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2011-04-06

    ...) Maritime Safety Committee (MSC 89) to be held May 11-20, 2011. The primary matters to be considered at MSC... --Technical assistance sub-programme in maritime safety and security --Capacity-building for the... business --Report of the Maritime Safety Committee Members of the public may attend these two meetings up...

  6. Technical support for geopressured-geothermal well activities in Louisiana

    International Nuclear Information System (INIS)

    John, C.J.

    1994-01-01

    The US Department of Energy has operated continuous-recording, microearthquake monitoring networks at geopressured-geothermal test well sites since 1980. These microseismic networks were designed to detect microearthquakes indicative of fault activation and/or subsidence that can potentially result from the deep subsurface withdrawal and underground disposal of large volumes of brine during well testing. Seismic networks were established before the beginning of testing to obtain background levels of seismicity. Monitoring continued during testing and for some time after cessation of flow testing to assess any delayed microseismicity caused by the time dependence of stress migration within the earth. No flow testing has been done at the Hulin well since January 1990, and the Pleasant Bayou well has been shut down since September 1992. Microseismic monitoring continued at the Hulin and Pleasant Bayou sites until 31 December 1992, at which time both operations were shut down and field sites dismantled. During 1992, the networks recorded seismic signals from earthquakes, sonic booms, geophysical blasting, thunderstorms, etc. However, as in previous years, no local microseismic activity attributable to geopressured-geothermal well testing was recorded

  7. The international ISOE programme. ISOE IAEA technical centre activities

    International Nuclear Information System (INIS)

    Gustafsson, M.

    1996-01-01

    The objective of the sub-programme on Occupational Radiation Protection in the International Atomic Energy Agency, IAEA, is to promote a harmonized approach to optimizing occupational radiation protection by developing guidelines for controlling radiation doses in the workplace and on current occupational radiation protection techniques. A significant part of this programme is the provision of assistance to developing member states to bring their radiation safety infrastructure to an appropriate level for the usage of radiation in the state. In consistence with these objectives the IAEA has been involved with the ISOE programme from its inception and has contributed actively to its growth. In 1993 an arrangement was agreed between the IAEA and the Nuclear Energy Agency, NEA, by which the IAEA co-sponsors ISOE inviting those IAEA member states which are not members of the NEA to participate cost-free in the programme. (author)

  8. Yucca Mountain Project: A summary of technical support activities, January 1987--June 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report is a summary of the technical support activities of Mifflin ampersand Associates, Inc., during the 18-month period beginning 01 January 1987 and ending on 30 June 1988. It covers the following topics: Vadose zone drilling site selection, permits and quality assurance (QA) procedures; climate change; geochemistry, mineralogy; disturbed zone; hydrogeology; and review of technical documents. The report is organized by generally discussing each topic from the following perspectives: issue(s), objective(s) of activity, finding(s), interpretation of finding(s), additional work needed, recommended program, and existing program

  9. DOE technical standards list: Directory of DOE and contractor personnel involved in non-government standards activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The body of this document contains a listing of DOE employees and DOE contractors who have submitted form DOE F 1300.2, Record of Non-Government Standards Activity, which is attached to the end of this document and to DOE Order 1300.2A. Additional names were added from rosters supplied by non-Government standards bodies. The committees or governing bodies in which the person participates is listed after each name. An asterisk preceding the committee notation indicates that the person has identified himself or herself as the DOE representative on that committee. Appendices to this document are also provided to sort the information by the parent employment organization, by non-Government standards activity, and by the proper names of the non-Government standards organizations and committees. DOE employees and contractors listed in this TSL are those recorded as of July 1, 1996.

  10. Report to the DOE Nuclear Data Committee

    International Nuclear Information System (INIS)

    Lundy, J.C.; Perey, F.G.

    1980-04-01

    This report was prepared for the DOE Nuclear Data Committee and covers work performed at ORNL since April 1979 in areas of nuclear data of relevance to the US applied nuclear energy program. The report was mostly generated through a review of abstracts of work completed to the point of being subjected to some form of publication in the open literature, formal ORNL reports, ORNL technical memoranda, progress reports, or presentation at technical conferences. As much as possible the complete abstract of the original publication is reproduced with only minor editing. In a few cases progress reports were written specifically for this publication. The editors selected the materials to be included in this report on the basis of perceived interests of DOE Nuclear Data Committee members and cannot claim completeness. Material is grouped as follows: Nuclear Cross Sections for Technology conference, cross section measurements, data analyses, and Nuclear Data Project activities for 1979. 2 figures

  11. Drug and Therapeutics (D & T) committees in Dutch hospitals : a nation-wide survey of structure, activities, and drug selection procedures

    NARCIS (Netherlands)

    Fijn, R; Brouwers, JRBJ; Knaap, RJ; De Jong-Van den Berg, LTW

    Aims To determine structure, activities and drug selection processes used by Dutch hospital drug and therapeutics (D & T) committees. Methods A pretested structured survey questionnaire based on the Australian process and impact indicators, previous research, and consultation of professionals was

  12. 5 CFR 591.241 - What are the key activities of the COLA Advisory Committees?

    Science.gov (United States)

    2010-01-01

    ... SERVICE REGULATIONS ALLOWANCES AND DIFFERENTIALS Cost-of-Living Allowance and Post Differential-Nonforeign...) The COLA Advisory Committees may— (1) Advise and assist OPM in planning living-cost surveys; (2) Provide or arrange for observers for data collection during living-cost surveys; (3) Advise and assist OPM...

  13. 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.

  14. Utilization of small-amount of radioactive isotope. Report of Technical Committee for Using Minor Radioactive Sources, Section of Physical Science and Industry, JRIAS. (1)

    International Nuclear Information System (INIS)

    1999-01-01

    The report of this series is a summary of considerations made by the committee which was founded in January, 1991, for stimulating the utilization of small-amount radioactive isotopes. The present report (1) is composed of three chapters concerning the purpose above mentioned and achievement of the committee, and reasonable regulation for the sealed isotopes. For the purpose, analysis was made for the present states of small-amount radioisotope utilization and of legal regulation and proposals were done by the committee. In the past, the first (1/1, 1991-5/31, 1992) and second (6/1, 1992 5/31, 1994) terms of the committee investigated the present states of utilization and safety handling in Japan and foreign countries, methods for stimulation, education and re-evaluation of the past trials for technology of those sub-legal isotopes together with translation of IAEA SAFETY SERIES No. 104 into Japanese, which was published in the journal Radioisotopes vol.44 (1995), for reference of the present states in Japan and foreign countries. In the chapter of proposal for the reasonable regulation for the sealed isotopes, the present committee investigated the present states of utilization of the industrial instruments and daily necessities which are equipped with small-amount radioisotopes, their legal and safety problems involved and the basis of calculation of exemption level, and made proposals for reasonable regulation. (K.H.)

  15. Mark II containment program load evaluation and acceptance criteria; Generic Technical Activity A-8

    International Nuclear Information System (INIS)

    Anderson, C.J.

    1981-08-01

    The report provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark II pressure-suppression containment design. This report concludes NRC Generic Technical Activity A-8, 'Mark II Containment Pool Dynamic Loads,' which has been designated an 'Unresolved Safety Issue' pursuant to Section 210 of the Energy Reorganization Act of 1974

  16. Standing Concertation Committee

    CERN Document Server

    HR Department

    2010-01-01

    Main issues examined at the meeting of 2 October 2009 The October 2009 meeting of the Standing Concertation Committee was entirely devoted to preparation of TREF’s meeting on 21-22 October. The Committee took note of, discussed and agreed on clarifications needed to some of the documents and presentations that the Management intended to submit and/or present to TREF on the following subjects: Equal opportunities The Committee took note of a preliminary report on equal opportunities at CERN drawn up by D. Chromek-Burckhart, the Equal Opportunities Officer, and T. Smith, Chairman of the Equal Opportunities Advisory Panel, containing in particular a proposal for a new process for resolving harassment conflicts. Technical analysis of the CERN Health Insurance Scheme - Actuary’s Report The Committee took note of a presentation by P. Charpentier, Chairman of the CERN Health Insurance Supervisory Board (CHIS Board), on the 2009 actuarial report on the CERN Health Insurance Scheme (CHIS). Th...

  17. IPN - Orsay Report of activity 1998-1999. General activities. Technical Development

    International Nuclear Information System (INIS)

    Pouthas, Joel; Hutin, Christiane; Rivenez, Jean-Philippe

    2000-01-01

    spectrometer and for HADES experiment. Also the progress in developing the equipment for G0 experiment, VAMOS spectrometer, the large surface annular telescope and EUROBALL 4 detector is described. Finally in the chapter four there are reported works on developing a peak sensing ADC, a VXI D size card for EXOGAM,and data acquisition systems. The first volume begins with short reports of activity from the technical and general servicing departments. The second volume of the IPNO Report presents the results of the Research Division

  18. Activities of special committee on 'quality assurance of accountancy analysis for safeguards'

    International Nuclear Information System (INIS)

    2010-01-01

    For the long-term stable operation of nuclear fuel cycle facilities, it is essential to satisfy the requirements of IAEA safeguards agreement. It could be attained by precise implementation of accountancy analysis of nuclear materials and application of Destructive Analysis (DA) which enables highly precise measurement is necessary. The requirements to maintain and improve the precision of DA are supposed to grow along with nuclear fuel cycle fully in progress and Pu handling amount increases. In order to maintain long-term stability of quality level of accountancy analysis for safeguards, a special committee on 'Quality Assurance (QA) for Accountancy /Safeguards analysis' was established at Atomic Energy Society Japan supported by INNM-Japan Chapter. Experts of safeguards analysis, reference materials, statistics and QA were gathered and drafted the committee standard document for isotope dilution mass spectrometry, the major accountancy analysis technique for Pu and U, supported Pu standard preparation at JAEA and summarized the items needed for QA of DA. (author)

  19. Introducing active learning pedagogy into a technical and vocational education and training academy in Kurdistan, Iraq

    Science.gov (United States)

    Dickson, Martina; Ladefoged, Svend Erik

    2017-10-01

    This article focuses on a teaching methodology project which investigated issues of teaching quality at a technical and vocational education and training (TVET) academy in Kurdistan, Northern Iraq. The academy was established in 2012 to provide unemployed youth with TVET, particularly workplace-relevant training. A needs analysis showed that the academy's teachers were mainly skilled in technical content areas rather than in pedagogy. Perhaps as a result, predominantly teacher-centred approaches to teaching were observed. However, teaching and learning in TVET, by its very definition, must consider active learning and practical training as core to its vocational purpose. Moreover, technical and pedagogical skills are intrinsically linked, since a teacher cannot effectively pass on technical skills without the necessary pedagogical skills to do so. It is on this premise that the authors of this article based their project, which was designed for the purpose of upgrading the teachers' pedagogical skills to incorporate more active learning strategies and practical work. Comparison of observation logs and feedback sessions at the conclusion of their project provided evidence that whilst some of the teachers' pedagogical skills had shifted towards using more dynamic teaching strategies, interviews strongly indicated that there was also some reluctance to incorporate active learning. In their conclusion, the authors suggest that the insights gained from this project could be further empirically examined in a larger, multi-institutional study.

  20. 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, 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 testing particulars for many mechanical, physical, thermal, properties and performance of these materials. As a result these standards provide 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, nearly 50 standards since the Committees founding in 1986. This paper provides a retrospective review of the 30 years of ASTM Committee C28 including a graphical pictogram listing of C28 standards along with examples of the tangible benefits of advanced ceramics standards to demonstrate their practical applications.

  1. French butane propane committee. 2003 activity report; Comite Francais du Butane et du Propane. Rapport d'activite 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-05-01

    This activity report presents the 2003 status of the actions carried out by the French butane and propane committee (CFBP) for the development of the liquefied petroleum gas (LPG) industry in France. While the past year has seen the butane, propane and LPG-fuel sales following the decay started 4 years ago, in 2004 the CFBP has reinforced its actions of public information about the LPG energy choice and has carried out several projects in order to improve the safety of LPG tanks and storage facilities, one of the first concern of LPG industry. (J.S.)

  2. ACTIVE METHODOLOGY AS A TEACHING AND PREPAREDNESS TOOL IN THE TECHNICAL COURSE OF LOGISTICS

    Directory of Open Access Journals (Sweden)

    Juliana ferreira de Vales

    2018-03-01

    Full Text Available With the change of the profile of the student, the educational institutions are following new forms for teaching-learning; and within this scenario the Active Methodologies have a great role to provide students with autonomy. The article aims to present the use of Active Methodologies as a teaching and learning tool in the logistics technical course, using the methods Flipped Classroom and Problem-Based Learning (PBL, with the aim of showing the effectiveness of both methods in technical education. For the elaboration of this article the methods used were: bibliographic research and direct observation. The implementation of the Active Methodologies makes the students more interested in the course, besides being an excellent pedagogical resource and an additional motivation for the students.

  3. 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*.

  4. ITER technology R and D progress report. Report by the Director. ITER technical advisory committee meeting, 25-27 June 2000, St. Petersburg

    International Nuclear Information System (INIS)

    2001-01-01

    The overall philosophy for the ITER design has been to use established approaches through detailed analysis and to validate their application to ITER through technology R and D, including fabrication of full scale or scalable models of key components. All this R and D work has been done for ITER under collaboration among the Home Teams, with a total resource of about 660 KIUA. R and D issues for ITER-FEAT are almost the same as for the 1998 ITER design. Major developments and fabrication have been completed and tests have significantly progressed. The technical output from the R and D validates the technologies and confirms the manufacturing techniques and quality assurance incorporated in the ITER design, and supports the manufacturing cost estimates for important key cost drivers. The testing of models is continuing to demonstrate their performance margin and/or to optimize their operational use. Their realisation offers insights useful for a possible future collaborative construction activity. Valuable and relevant experience has already been gained in the management of industrial scale, cross-party ventures. The successful progress of these projects increases confidence in the possibility of jointly constructing ITER in an international project framework. The R and D present status is summarized in the following: details are given in Chapters 2 and 3. Significant efforts and resources have been devoted to the Seven Large R and D Projects which cover all the major key components of the basic machine of ITER and their maintenance tools

  5. Technical and Physical Activities of Small-Sided Games in Young Korean Soccer Players.

    Science.gov (United States)

    Joo, Chang H; Hwang-Bo, Kwan; Jee, Haemi

    2016-08-01

    Joo, CH, Hwang-Bo, K, and Jee, H. Technical and physical activities of small-sided games in young Korean soccer players. J Strength Cond Res 30(8): 2164-2173, 2016-The aim of this study was to examine the technical aspects and physical demands during small-sided games (SSGs) with different sized pitches in young Korean soccer players. Participants were randomly selected during a nationally held youth competition. Three different game formats were used: SSG8 (8 vs. 8 played on a small-sized field [68 × 47 m]), RSG8 (8 vs. 8 played on a regular-sized field [75 × 47 m]), and RSG11 (11 vs. 11 played on a regular-sized field). Eleven technical (ball touches, passes, and shots) and 6 physical demand variables (exercise frequency by intensity) were observed and analyzed. Same variables were also analyzed for the goalkeepers. As a result, SSG8 and RSG8 showed significantly greater numbers of technical plays in 5 and 4 variables in comparison to RSG11, respectively. In addition, although the exercise intensities increased slightly in both SSG formats, the amount was within the similar range as previous reports. In conclusion, the SSGs with reduced number of players may be referred in young players to effectively train them in technical aspects of the game by allowing greater ball exposure time without excessive physical demands. Various confounding factors such as pitch dimension should be carefully considered for training specific technical and physical variables in young Korean players.

  6. Organization of the ITER Co-ordinated Technical Activities International Team

    International Nuclear Information System (INIS)

    2001-01-01

    At its meeting in Toronto on 7 November 2001, the ITER Co-ordinated Technical Activities (CTA) project board took note of the organizational arrangements for the CTA International Team at the Garching and Naka joint work sites. The organization chart of the team remains almost unchanged from that of the ITER Engineering Design Activities (EDA). However, there is no special division responsible for plasma and field control. Activities in plasma control will be taken over by the Physics Unit. This newsletter also includes the ITER CTA International Team structure

  7. Future nuclear regulatory challenges. A report by the NEA Committee on Nuclear Regulatory Activities

    International Nuclear Information System (INIS)

    1998-01-01

    Future challenges are considered that may arise from technical, socio-economic and political issues; organizational, management and human aspects; and international issues. The perceived challenges have been grouped into four categories, each covered by a chapter. Technical issues are addressed that many present regulatory challenges in the future: ageing nuclear power plants. External changes to industry are considered next that have an effect on regulators, privatization, cost reduction consequences, commercialization etc. It is followed by the impacts of internal changes: organizational, managerial, human-resources, licensing, staff training etc. Finally, international issues are discussed with potential regulatory impact. (R.P.)

  8. Analysis of the sponsorship activities of the Organizing committee «Kiev City marathon – 2014»

    Directory of Open Access Journals (Sweden)

    Olena Yarmolyuk

    2015-04-01

    Full Text Available Purpose: to share the experience of the marketing technologies application in the physical culture and sports sphere and to improve the commercial activities of sports organizations during the planning and holding the mass sporting events. Material and Methods: the basic forms and methods of the sponsorship activities of the Organizing Committee of the competition «Kiev Marathon – 2014» were analyzed with system analysis, SWOT-analysis and sociological questioning (12 specialists from the Organizing Committee of «Kiev City Marathon – 2014» and 95 visitors of the «Kiev City Marathon – 2014» were questioned. Results: the best way for obtaining the sponsorship is to use the level-approach by the organizers, which means that all sponsors were divided on different levels and each one had certain privileges. It had resulted in appropriate sponsorship agreements. Conclusions: the results of research given in the article will enable professionals to most effectively search and work with the sponsors in the physical culture and sports sphere, as well as to introduce modern mechanisms of interaction between businesses and sporting organizations.

  9. RILEM technical committee 195-DTD recommendation for test methods for AD and TD of early age concrete Round Robin documentation report : program, test results and statistical evaluation

    CERN Document Server

    Bjøntegaard, Øyvind; Krauss, Matias; Budelmann, Harald

    2015-01-01

    This report presents the Round-Robin (RR) program and test results including a statistical evaluation of the RILEM TC195-DTD committee named “Recommendation for test methods for autogenous deformation (AD) and thermal dilation (TD) of early age concrete”. The task of the committee was to investigate the linear test set-up for AD and TD measurements (Dilation Rigs) in the period from setting to the end of the hardening phase some weeks after. These are the stress-inducing deformations in a hardening concrete structure subjected to restraint conditions. The main task was to carry out an RR program on testing of AD of one concrete at 20 °C isothermal conditions in Dilation Rigs. The concrete part materials were distributed to 10 laboratories (Canada, Denmark, France, Germany, Japan, The Netherlands, Norway, Sweden and USA), and in total 30 tests on AD were carried out. Some supporting tests were also performed, as well as a smaller RR on cement paste. The committee has worked out a test procedure recommenda...

  10. Pulsed Power Peer Review Committee Report

    International Nuclear Information System (INIS)

    BLOOMQUIST, DOUGLAS D.

    2002-01-01

    In 1993, the Government Performance and Results Act (GPRA, PL 103-62) was enacted. GPRA, which applies to all federal programs, has three components: strategic plans, annual performance plans, and metrics to show how well annual plans are being followed. As part of meeting the GRPA requirement in FY2002, a 15-member external review committee chaired by Dr. Alvin Trivelpiece (the Trivelpiece Committee) was convened by Sandia National Laboratories (SNL) on May 7-9, 2002 to review Sandia National Laboratories' Pulsed Power Programs as a component of the Performance Appraisal Process negotiated with the National Nuclear Security Administration of the Department of Energy (NNSA/DOE). The scope of the review included activities in high energy density physics (HEDP), inertial confinement fusion (ICF), radiation/weapon physics, the petawatt laser initiative (PW) and fast ignition, equation-of-state studies, radiation effects science and lethality, x-ray radiography, ZR development, basic research and pulsed power technology research and development, as well as electromagnetics and work for others. In his charge to the Committee, Dr. Jeffrey P. Quintenz, Director of Pulsed Power Sciences (Org. 1600) asked that the evaluation and feedback be based on three criteria: (1) quality of technical activities in science, technology, and engineering, (2) programmatic performance, management, and planning, and (3) relevance to national needs and agency missions. In addition, the director posed specific programmatic questions. The accompanying report, produced as a SAND document, is the report of the Committee's finding

  11. The technical analysis of the stock exchange and physics: Japanese candlesticks for solar activity

    Science.gov (United States)

    Dineva, C.; Atanasov, V.

    2013-09-01

    In this article, we use the Japanese candlesticks, a method popular in the technical analysis of the Stock/Forex markets and apply it to a variable in physics-the solar activity. This method is invented and used exclusively for economic analysis and its application to a physical problem produced unexpected results. We found that the Japanese candlesticks are convenient tool in the analysis of the variables in the physics of the Sun. Based on our observations, we differentiated a new cycle in the solar activity.

  12. 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)

  13. A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

    International Nuclear Information System (INIS)

    Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

    2009-11-01

    This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

  14. Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

    International Nuclear Information System (INIS)

    Lee, D.W.; Shingleton, K.L.

    1996-01-01

    Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated

  15. Report for fiscal 1995 on simple operation type CAD/CAM system development through international cooperation. Committee activity record; 1995 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

    1996-03-01

    This paper reports the committee activities in fiscal 1995 on research cooperation for developing an electronics design and production aid system of simple operation type (MATIC). This fiscal year has decided the directionality of MATIC promotion by activities carried out by the different committees. These activities relate to research and development themes, the basic policies of the research and development along with the themes, research and development themes linked with overseas countries, and promotion methods. The working group (WG)I has discussed and deliberated specific research and development items to promote research and development of automobiles and components thereof as the promotion theme, promotion of the research and development, and technical problems. The committee consists of researchers at the related corporations participated in MATIC. The WGII has taken up household appliances and parts thereof, and the WGIII textiles and apparels as the research and development themes, and given specific discussions for promoting the research and development. The paper also reports the activities taken by different committees for promotion of the production-based futuristic type integrated information system, and promotion of the MATIC technologies, operation and cooperation. (NEDO)

  16. Report for fiscal 1995 on simple operation type CAD/CAM system development through international cooperation. Committee activity record; 1995 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

    1996-03-01

    This paper reports the committee activities in fiscal 1995 on research cooperation for developing an electronics design and production aid system of simple operation type (MATIC). This fiscal year has decided the directionality of MATIC promotion by activities carried out by the different committees. These activities relate to research and development themes, the basic policies of the research and development along with the themes, research and development themes linked with overseas countries, and promotion methods. The working group (WG)I has discussed and deliberated specific research and development items to promote research and development of automobiles and components thereof as the promotion theme, promotion of the research and development, and technical problems. The committee consists of researchers at the related corporations participated in MATIC. The WGII has taken up household appliances and parts thereof, and the WGIII textiles and apparels as the research and development themes, and given specific discussions for promoting the research and development. The paper also reports the activities taken by different committees for promotion of the production-based futuristic type integrated information system, and promotion of the MATIC technologies, operation and cooperation. (NEDO)

  17. ITER EDA newsletter. V. 3, no. 1. (International Thermonuclear Experimental Reactor Engineering Design Activities)

    International Nuclear Information System (INIS)

    1994-01-01

    This issues of the ITER EDA (Engineering Design Activities) Newsletter contains reports on the Fourth ITER Management Advisory Committee Meeting (MAC) held at San Diego, USA, 13-14 January, 1994, a Technical Committee Meeting on Plasma Equilibrium and Control held at Naka, Japan, 9-12 November 1993, and a Technical Committee Meeting on Radio-Frequency Heating and Current Drive held in Garching, Germany, 21-26 October 1993

  18. Active Control of Thermostatic Loads for Economic and Technical Support to Distribution Grids

    DEFF Research Database (Denmark)

    Bhattarai, Bishnu Prasad; Mendaza, Iker Diaz de Cerio; Bak-Jensen, Birgitte

    2016-01-01

    Active control of electric water heaters (EWHs) is presented in this paper as a means of exploiting demand flexibility for supporting low-voltage (LV) distribution grids. A single-node model of an EWH is implemented in DIgSILENT PowerFactory using a thermal energy balancing equation and three...... decentralized control schemes are designed to ensure consumer comfort, economic benefit to the consumer, and technical support to LV grids. First, a price-based control that adaptively adjusts an allowable energy band per electricity price is implemented to ensure economic benefit. Next, an adaptive update...... of the energy band is done based on feeder loading to respect thermal grid constraints. Finally, a voltage-based control is implemented to provide real-time voltage support to the LV grids. Simulation results demonstrate the capability of the presented method to realize both economic and technical advantages...

  19. Strategy for nuclear technical cooperation between Korea and U.S.A

    International Nuclear Information System (INIS)

    Kim, Kyoung Pyo; Kim, Young Min

    1998-12-01

    The Republic of Korea maintains joint coordination committee meeting in the field of nuclear technology with seven countries throughout the world. Among the committees, the R.O.K. - U.S.A. Joint Standing Committee on Nuclear Energy Cooperation (JSCNET) is regarded as one of the most active committees considering the long cooperative relationship relationship between the two countries. The cooperative programs between two countries range not only technical issues but also nuclear policy and safeguards endeavors. It is noted that at present there are eight items for co-operation in nuclear policy field, fourteen technical cooperation programs, thirteen safety related items for mutual co-operation, and six items for safeguards concerns. KAERI plays a key role in the implementation of joint cooperative programs as has been during the past. Among the various cooperative programs currently on-going, thirteen technical items and two safety programs are being initiated by KAERI. (author). 1 tab., 1 fig

  20. 76 FR 11195 - Request for Nominations of Members To Serve on the Census Scientific Advisory Committee

    Science.gov (United States)

    2011-03-01

    ... technical expertise from the following disciplines: demography, economics, geography, psychology, statistics... Advisory Committee are essential for sustained Advisory Committee membership as well as submission of... must have scientific and technical expertise in such areas as demography, economics, geography...

  1. Match-to-match variation in physical activity and technical skill measures in professional Australian Football.

    Science.gov (United States)

    Kempton, Thomas; Sullivan, Courtney; Bilsborough, Johann C; Cordy, Justin; Coutts, Aaron J

    2015-01-01

    To determine the match-to-match variability in physical activity and technical performance measures in Australian Football, and examine the influence of playing position, time of season, and different seasons on these measures of variability. Longitudinal observational study. Global positioning system, accelerometer and technical performance measures (total kicks, handballs, possessions and Champion Data rank) were collected from 33 players competing in the Australian Football League over 31 matches during 2011-2012 (N=511 observations). The global positioning system data were categorised into total distance, mean speed (mmin(-1)), high-speed running (>14.4 kmh(-1)), very high-speed running (>19.9 kmh(-1)), and sprint (>23.0 kmh(-1)) distance while player load was collected from the accelerometer. The data were log transformed to provide coefficient of variation and the between subject standard deviation (expressed as percentages). Match-to-match variability was increased for higher speed activities (high-speed running, very high-speed running, sprint distance, coefficient of variation %: 13.3-28.6%) compared to global measures (speed, total distance, player load, coefficient of variation %: 5.3-9.2%). The between-match variability was relativity stable for all measures between and within AFL seasons, with only few differences between positions. Higher speed activities (high-speed running, very high-speed running, sprint distance), but excluding mean speed, total distance and player load, were all higher in the final third phase of the season compared to the start of the season. While global measures of physical performance are relatively stable, higher-speed activities and technical measures exhibit a large degree of between-match variability in Australian Football. However, these measures remain relatively stable between positions, and within and between Australian Football League seasons. Copyright © 2013 Sports Medicine Australia. Published by Elsevier Ltd

  2. Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports. Resolution of generic technical activity A-12

    International Nuclear Information System (INIS)

    Snaider, R.P.; Hodge, J.M.; Levin, H.A.; Zudans, J.J.

    1979-10-01

    This report summarizes work performed by the Nuclear Regulatory Commission staff and its contractor, Sandia Laboratories, in the resolution of Generic Technical Activity A-12, ''Potential for Low Fracture Toughness and Lamellar Tearing in PWR Steam Generator and Reactor Coolant Pump Supports.'' The report describes the technical issues, the technical studies performed by Sandia describes the technical issues, the technical studies performed by Sandia Laboratories, the NRC staff's technical positions based on these studies, and the staff's plan for implementing its technical positions. It also provides recommendations for further work. The complete technical input from Sandia Laboratories is appended to the report

  3. Annual activities report of Brazilian Aerospace Technical Center -CTA/IEAv - 1989; Relatorio anual de atividades - CTA/IEAv - 1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    This document reports the research activities on nuclear physics and reactors physics and engineering in the Brazilian Aerospace Technical Center/Advanced Studies Institute, Sao Paulo State, in the year of 1989.

  4. Annual activities report of Brazilian Aerospace Technical Center -CTA/IEAv - 1989; Relatorio anual de atividades - CTA/IEAv - 1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-12-31

    This document reports the research activities on nuclear physics and reactors physics and engineering in the Brazilian Aerospace Technical Center/Advanced Studies Institute, Sao Paulo State, in the year of 1989.

  5. Ian Taylor MBE MP Chairman Parliamentary and Scientific Committee, United Kingdom (second from left) with (from left to right) CMS Technical Coordinator A. Ball, CMS Spokesperson Tejinder (Jim) Virdee and Adviser to the Director-General J. Ellis on 2 November 2009.

    CERN Multimedia

    Maximilien Brice; CMS

    2009-01-01

    Ian Taylor MBE MP Chairman Parliamentary and Scientific Committee, United Kingdom (second from left) with (from left to right) CMS Technical Coordinator A. Ball, CMS Spokesperson Tejinder (Jim) Virdee and Adviser to the Director-General J. Ellis on 2 November 2009.

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

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  7. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, C.A., Westinghouse Hanford

    1996-07-17

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  8. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, C.A.

    1996-09-20

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  9. Goals and activities of the JICA technical cooperation project on reduction of seismic risk in Romania

    International Nuclear Information System (INIS)

    Vacareanu, R.; Kato, H.

    2007-01-01

    Japan International Cooperation Agency (JICA) Technical Cooperation Project on Reduction of Seismic Risk for Buildings and Structures started in Romania on October 1, 2002. The aim of the Project is to strengthen the capacity of earthquake disaster related activities in Romania. The Project approval is the result of four years of intensive efforts made by professionals from Technical University of Civil Engineering Bucharest (UTCB), Ministry of Transport, Constructions and Tourism (MTCT), Romania, National Building Research Institute (INCERC) Bucharest, JICA, Building Research Institute (BRI), Tsukuba, and National Institute for Land, Infrastructure and Management (NILIM), Tsukuba, Japan. The duration of the Project is five years. The implementing agency is the National Center for Seismic Risk Reduction (NCSRR) as a public institution of national interest under MTCT. The activities are carried out by NCSRR in partnership with UTCB and INCERC. During the Project period, 29 young Romanian engineers were trained in Japan, 7 Japanese experts and 37 Japanese experts worked for long-term and short-term, respectively in Romania. Equipment for seismic instrumentation, dynamic characterization of soil and structural testing rising up approximately to 260 million yens (i.e. 2.17 million USD) were donated by JICA to Romania, through NCSRR. The total cost of the Project is roughly 7 million USD. The paper describes the main activities and results of the Project until the JICA Final Evaluation Mission (March 2007). (authors)

  10. Technical report: urinary tract infections in febrile infants and young children. The Urinary Tract Subcommittee of the American Academy of Pediatrics Committee on Quality Improvement.

    Science.gov (United States)

    Downs, S M

    1999-04-01

    The Urinary Tract Subcommittee of the American Academy of Pediatrics Committee on Quality Improvement has analyzed alternative strategies for the diagnosis and management of urinary tract infection (UTI) in children. The target population is limited to children between 2 months and 2 years of age who are examined because of fever without an obvious cause. Diagnosis and management of UTI in this group are especially challenging for these three reasons: 1) the manifestation of UTI tends to be nonspecific, and cases may be missed easily; 2) clean voided midstream urine specimens rarely can be obtained, leaving only urine collection methods that are invasive (transurethral catheterization or bladder tap) or result in nonspecific test results (bag urine); and 3) a substantial number of infants with UTI also may have structural or functional abnormalities of the urinary tract that put them at risk for ongoing renal damage, hypertension, and end-stage renal disease (ESRD). To examine alternative management strategies for UTI in infants, a conceptual model of the steps in diagnosis and management of UTI was developed. The model was expanded into a decision tree. Probabilities for branch points in the decision tree were obtained by review of the literature on childhood UTI. Data were extracted on standardized forms. Cost data were obtained by literature review and from hospital billing data. The data were collated into evidence tables. Analysis of the decision tree was used to produce risk tables and incremental cost-effectiveness ratios for alternative strategies. Based on the results of this analysis and, when necessary, consensus opinion, the Committee developed recommendations for the management of UTI in this population. This document provides the evidence the Subcommittee used in the development of its recommendations. The Subcommittee agreed that the objective of the practice parameter would be to minimize the risk of chronic renal damage within reasonable economic

  11. 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

  12. 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

  13. Summary of the progress of reactor physics in Japan reviewing the activities related to NEA Committee on Reactor Physics

    International Nuclear Information System (INIS)

    Hirota, Jitsuya

    1984-09-01

    The progress of fast and thermal reactor physics, fusion neutronics and shielding researches in these twenty years can be clearly recognized in the reviews of reactor physics activities in Japan which had been perpared by the Special Committee on Reactor Physics: the joint committee under Atomic Energy Society of Japan and JAERI. Many topics of those discussed at the NEACRP meetings concerned fast reactor physics. Information exchange on the topics such as adjustment of group cross sections by integral data, central worth discrepancy, sodium void effect and heterogeneous core stimulated the researches in Japan. And achievements in Japan including those in the JAERI Fast Critical Facility FCA were reported and contributed largely to the international co-operation. In addition, the contribution from Japan was also made concerning a study of fusion blanket. Among various specialists' meetings recommended by NEACRP, those on nuclear data and benchmarks for reactor shielding were often held since 1973 and helpful to the progress of shielding researches in Japan. The Third Specialists' Meeting on Reactor Noise (SMORN-III) was held in Tokyo in 1981, indicating the recent progress in safety-related applications of reactor noise analysis. The NEACRP benchmark tests were quite useful to the progress of reactor physics in Japan, which included the benchmark calculations of BWR lattice cell, key parameters and burn-up characteristics of a large LMFBR, FBR and PWR shielding, and so on. It may be noted that the benchmark test on reactor noise analysis methods was successfully conducted by Japan in connection with SMORN-III. In addition, the co-operation was positively made to the compilation of light water lattice data, and the preparation of reviews on actinide production and burn-up, and blanket physics. (J.P.N.)

  14. 7 CFR 1728.50 - Removal of an item from listing or technical acceptance.

    Science.gov (United States)

    2010-01-01

    ... equipment will be notified in writing of a proposal to remove such item from the listing or technical... unanimous, the item will be referred to Technical Standards Committee “B.” Written notice of Technical...” decision, a sponsor may appeal in writing to Technical Standards Committee “B” to review Committee “A's...

  15. Pump Management Committees and sustainable community water ...

    African Journals Online (AJOL)

    PMCs), technically known as Water and Sanitation Committees (WATSAN) in the water sector, are institutionalized organs for community water management. A survey of twenty-seven (27) of these institutions in six districts across the Upper ...

  16. 78 FR 76599 - Nuclear Energy Advisory Committee

    Science.gov (United States)

    2013-12-18

    ... DEPARTMENT OF ENERGY Nuclear Energy Advisory Committee AGENCY: Office of Nuclear Energy..., General Services Administration, notice is hereby given that the Nuclear Energy Advisory Committee (NEAC... to the Department of Energy's Office of Nuclear Energy on complex science and technical issues that...

  17. International Collaboration on Building Local Technical Capacities for Monitoring Volcanic Activity at Pacaya Volcano, Guatemala.

    Science.gov (United States)

    Escobar-Wolf, R. P.; Chigna, G.; Morales, H.; Waite, G. P.; Oommen, T.; Lechner, H. N.

    2015-12-01

    Pacaya volcano is a frequently active and potentially dangerous volcano situated in the Guatemalan volcanic arc. It is also a National Park and a major touristic attraction, constituting an important economic resource for local municipality and the nearby communities. Recent eruptions have caused fatalities and extensive damage to nearby communities, highlighting the need for risk management and loss reduction from the volcanic activity. Volcanic monitoring at Pacaya is done by the Instituto Nacional de Sismologia, Vulcanologia, Meteorologia e Hidrologia (INSIVUMEH), instrumentally through one short period seismic station, and visually by the Parque Nacional Volcan de Pacaya y Laguna de Calderas (PNVPLC) personnel. We carry out a project to increase the local technical capacities for monitoring volcanic activity at Pacaya. Funding for the project comes from the Society of Exploration Geophysicists through the Geoscientists Without Borders program. Three seismic and continuous GPS stations will be installed at locations within 5 km from the main vent at Pacaya, and one webcam will aid in the visual monitoring tasks. Local educational and outreach components of the project include technical workshops on data monitoring use, and short thesis projects with the San Carlos University in Guatemala. A small permanent exhibit at the PNVPLC museum or visitor center, focusing on the volcano's history, hazards and resources, will also be established as part of the project. The strategy to involve a diverse group of local collaborators in Guatemala aims to increase the chances for long term sustainability of the project, and relies not only on transferring technology but also the "know-how" to make that technology useful. Although not a primary research project, it builds on a relationship of years of joint research projects at Pacaya between the participants, and could be a model of how to increase the broader impacts of such long term collaboration partnerships.

  18. Technical issues of fabrication technologies of reduced activation ferritic/martensitic steels

    International Nuclear Information System (INIS)

    Tanigawa, Hiroyasu; Sakasegawa, Hideo; Hirose, Takanori

    2013-01-01

    Highlights: • The key technical issues of RAFM steel fabrication are the control of Ta, and deoxidation of the steel with a limited amount of Al addition. • Addition of Ta with poor deoxidation might results in the agglomeration of inclusions at 1/2t position. • ESR was proved to be effective removing Ta oxide inclusions and avoiding agglomeration of inclusions at 1/2t position, and achieving low oxygen concentration. -- Abstract: The key issue for DEMO application is that Reduced activation ferritic/martensitic (RAFM) steels fabrication technologies has to be highly assured, especially with respect to high availability, reliability and reduced activation capability on the DEMO level fabrication, which requires not a few tons but thousand tons RAFM fabrication. One of the key technical issues of RAFM fabrication is the control of Ta, and deoxidation of the steel with a limited amount of Al addition. The series of F82H (Fe–8Cr–2W–V, Ta) melting revealed that Ta have tendency to form oxide on melting process, and this will have large impact on reliability of the steels. Al is also the key elements, as it is commonly used for deoxidation of steels, and achieving lower oxygen level is essential to obtain good mechanical properties, but the maximum concentration of Al is limited in view of reduced activation capability. These tendency and limitation resulted in the Ta oxide agglomeration in the middle of plate, but the remelting process, ESR (electro slag remelting), was found to be successful on removing those Ta oxides

  19. Domestic activity for technical development of the APR1400's RCP performance test

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seok; Kim, Seok; Bae, Byung-Uhn; Cho, Yun-Jae; Kim, Yeon-Sik; Jeon, Woo-Jin; Yun, Young-Jung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The thermal hydraulic and electric capability of the RCP test facility (RCPTF) covers up to 18.5 MPa, 343 .deg. C, 11.7 m{sup 3}/s, and 14.0 MW in the design pressure, temperature, flow rate, and the maximum electric power, respectively. In 2013, commissioning test had been performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance verification and evaluation capability of the RCP performance. After finishing the commissioning and modification of the RCPTF, type test for the new-type RCP had been performed successfully. In this paper, several technical issues developed in the 2013 and the type test's method and results will be described. In the present paper, the technical activities for the development of the verification test of APR1400's RCP are described. KAERI has completed the full set of technology development, prerequisite for the RCP verification test, and now on the way to perform a test for the sealing capacity of the seal assembly during the Station Block Out (SBO) condition of APR1400.

  20. 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...

  1. 75 FR 64390 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2010-10-19

    ...-eighth Session of the International Maritime Organization's (IMO) Maritime Safety Committee to be held at... --Technical assistance sub-programme in maritime safety and security --Capacity-building for the... --Measures to enhance maritime security --Goal-based new ship construction standards --LRIT-related matters...

  2. 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...

  3. 77 FR 21619 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-04-10

    ... of the International Maritime Organization's (IMO) Marine Safety Committee to be held at the IMO... gases; Implementation of the STCW Convention; Technical assistance sub-programme in maritime safety and...: Consideration and adoption of amendments to mandatory instruments; Measures to enhance maritime security; Goal...

  4. 76 FR 7870 - Agency Information Collection Activities: Cybersecurity and Communications Technical Assistance...

    Science.gov (United States)

    2011-02-11

    ...: Technical Assistance Request and Evaluation. Form: DHS Form 9042, DHS Form 9043. OMB Number: 1670-NEW... technical assistance requests from each State and territory. The Technical Assistance Evaluation Form is... will be submitted electronically. Evaluation forms may be submitted electronically or in paper form...

  5. Activity theory and genre ecology: Conceptual tools for understanding technical communication

    Directory of Open Access Journals (Sweden)

    Winberg, Christine

    2005-12-01

    Full Text Available This paper reports on a year-long project in an architectural technology department, which studied students’ oral language development in plenary discussions in a first year History and Appreciation of Architecture course. Data was obtained by videotaping classroom activities, and by interviewing the lecturer and students who were participants in the course. The data was analysed, using categories suggested by Activity Theory. The category of ‘rules’ was selected from the activity system for further analysis, using a Genre Ecology approach. The findings of the study show how technical communication is managed within a classroom based activity system comprising lecturer and students, and graphic and verbal texts, in a context of learning. Learning, teaching, and expert discourses of the architectural review genre interact and are negotiated by participants. Through participation in plenary discussion, students from diverse backgrounds contribute to one another’s experience of architectural design, and by valuing and responding to students’ contributions, the lecturer facilitates students’ understanding of the ‘rules’ of architectural communication, and enables students to access an expanded repertoire of the genre of architectural review.

  6. Financing technical-medical activities. CT scanner example in France (1986)

    International Nuclear Information System (INIS)

    Meyer, C.; Lefaure, C.; Fagnani, F.

    1988-01-01

    To analyze the french methods for financing technical-medical activities as CT scanners, and to assess if they can face, or not, the management constraints of such activities a financial simulation has been executed. First, current expenditures are totalized (including depreciations and financial charges) with variations according to the numer of examinations per year. Costs are classified especially according to fixed and variable charges: the weight of fixed charges, especially equipment charges, is the most significant. It's very high in yearly expenditures. Most, that involves a very fast decreasing cost with increasing number of procedures. Second, consequences of such accounts are analyzed: - on private CT scanners, Payed with a charge per examination whatever would be the factor's cost; - on public CT scanners, payed with an annual allowance; in this case charges equal receipts whatever would be the cost for a procedure. Third, a break point is defined; either the annual activity is higher: there would be an excedent; either it is lower: there would be a deficit. Then, those results are reported to CT-scanners activity's data in France (1986). After all, financing systems themselves, are discussed and a few hypothesis to explain those desadjustments between charges and their financing way are suggested [fr

  7. Mark III LOCA-related hydrodynamic load definition. Generic technical activity B-10. Final report

    International Nuclear Information System (INIS)

    Fields, M.B.; Kudrick, J.A.

    1984-08-01

    This report, prepared by the staff of the Office of Nuclear Reactor Regulation and its consultants at the Brookhaven National Laboratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design. Its issuance completes NRC Generic Technical Activity B-10, Behavior of BWR Mark III Containment. On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric Company developed LOCA-related hydrodynamic load definitions for use in the design of the standard Mark III containment. The staff and its consultants have reviewed these load definitions and their bases and conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions. The staff approved acceptance criteria for LOCA-related hydrodynamic loads are provided in an appendix

  8. Mark III LOCA-related hydrodynamic load definition. Generic technical activity B-10

    International Nuclear Information System (INIS)

    1984-02-01

    This report, prepared by the staff of the Office of Nuclear Reactor Regulation and its consultants at the Brookhaven National Laboratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design. Its issuance completes NRC Generic Technical Activity B-10, Behavior of BWR Mark III Containment. On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric Company developed LOCA-related hydrodynamic load definitions for use in the design of the standard Mark III containment. The staff and its consultants have reviewed these load definitions and their bases conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions. The staff-approved acceptance criteria for LOCA-related hydrodynamic loads are provided in Appendix C of this report

  9. Materials selection as an interdisciplinary technical activity: basic methodology and case studies

    Directory of Open Access Journals (Sweden)

    M. Ferrante

    2000-04-01

    Full Text Available The technical activity known as Materials Selection is reviewed in its concepts and methodologies. Objectives and strategies are briefly presented and two important features are introduced and discussed; (i Merit Indices: a combination of materials properties, which maximises the objectives chosen by the designer and (ii Materials Properties Maps: a bi-dimensional space whose coordinates are pairs of properties in which materials can be plotted and compared directly in terms of their merit indices. A general strategy for the deduction of these indices is explained and a formal methodology to establish a ranking of candidate materials when multiple constraints intervene is presented. Finally, two case studies are discussed in depth, one related to materials substitution in the context of mechanical design and a less conventional case linking material selection to physical comfort in the home furniture industry.

  10. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

    International Nuclear Information System (INIS)

    Tanigawa, H.; Hirose, T.; Shiba, K.; Kasada, R.; Wakai, E.; Serizawa, H.; Kawahito, Y.; Jitsukawa, S.; Kimura, A.; Kohno, Y.; Kohyama, A.; Katayama, S.; Mori, H.; Nishimoto, K.; Klueh, R.L.; Sokolov, M.A.; Stoller, R.E.; Zinkle, S.J.

    2008-01-01

    Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. The RAFM F82H was developed in Japan with emphasis on high-temperature properties and weldability. Extensive irradiation studies have conducted on F82H, and it has the most extensive available database of irradiated and unirradiated properties of all RAFMs. The objective of this paper is to review the R and D status of F82H and to identify the key technical issues for the fabrication of an ITER test blanket module (TBM) suggested from the recent research achievements in Japan. This work clarified that the primary issues with F82H involve welding techniques and the mechanical properties of weld joints. This is the result of the distinctive nature of the joint caused by the phase transformation that occurs in the weld joint during cooling, and its impact on the design of a TBM will be discussed

  11. LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-10-01

    The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

  12. Alkali-Activated Mortars for Sustainable Building Solutions: Effect of Binder Composition on Technical Performance

    Directory of Open Access Journals (Sweden)

    Agnese Attanasio

    2018-02-01

    Full Text Available There is a growing interest in the construction sector in the use of sustainable binders as an alternative to ordinary Portland cement, the production of which is highly impacting on the environment, due to high carbon dioxide emissions and energy consumption. Alkali-activated binders, especially those resulting from low-cost industrial by-products, such as coal fly ash or metallurgical slag, represent a sustainable option for cement replacement, though their use is more challenging, due to some technological issues related to workability or curing conditions. This paper presents sustainable alkali-activated mortars cured in room conditions and based on metakaolin, fly ash, and furnace slag (both by-products resulting from local sources and relevant blends, aiming at their real scale application in the building sector. The effect of binder composition—gradually adjusted taking into consideration technical and environmental aspects (use of industrial by-products in place of natural materials in the view of resources saving—on the performance (workability, compressive strength of different mortar formulations, is discussed in detail. Some guidelines for the design of cement-free binders are given, taking into consideration the effect of each investigated alumino-silicate component. The technical feasibility to produce the mortars with standard procedures and equipment, the curing in room conditions, the promising results achieved in terms of workability and mechanical performance (from 20.0 MPa up to 52.0 MPa, confirm the potential of such materials for practical applications (masonry mortars of class M20 and Md. The cement-free binders resulting from this study can be used as reference for the development of mortars and concrete formulations for sustainable building materials production.

  13. Risks from electricity generation systems in the far future. Proceedings of a technical committee meeting on approaches for estimating and comparing risks from energy systems in the far future. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Comparative risk assessment of the health and environmental impacts of electricity generation systems can be used for providing information for decisions concerning choice of electricity generation systems and regulation of the systems. Since the beginning of 1990s, there have been several major studies of comparative risk assessment that have advanced the methodology and knowledge for the assessment of health and environmental impacts of electricity production systems. In those studies, many methodological issues were identified, and it was found that one of the major issues that influenced the results was the time period included in the risk assessment. In the results of recent studies, the impacts for long time periods are influential because of the accumulation of the impacts for more than 100 years and the large uncertainties in the estimations. Examples of such long term impacts are those from global climate change and potential impacts from radionuclides ad non-radioactive pollutants originating from nuclear and other electricity generation systems. It is generally expected that the estimates for longer term impacts have greater uncertainty. In order to enhance the comparative risk studies and the application of the results, the methodology and key issues for estimating the impacts for future :generations should be investigated, and approaches for the assessments should be established. In this connection, the IAEA Technical Committee Meeting TCM on Approaches for Estimating and Comparing Risks from Energy Systems in the Far Future was held at the IAEA Headquarters in Vienna, Austria, from 6 to 10 October 1997. This material contains the proceedings of the TCM held in October 1997, and the latest draft of the technical report, Long-Term Risks from Electricity Generation Systems

  14. Technical feasibility study for the D-T neutron monitor using activation of the flowing water

    International Nuclear Information System (INIS)

    Uno, Yoshitomo; Kaneko, Junichi; Nishitani, Takeo; Maekawa, Fujio; Tanaka, Teruya; Ikeda, Yujiro; Takeuchi, Hiroshi

    2001-03-01

    The experimental study of technical feasibility for the D-T neutron monitor using activation of the flowing water was performed at FNS/JAERI as the ITER/EDA R and D Task T499. The temporal resolution for pulsed neutrons was measured and dependence of the temporal resolution on flowing velocity was studied. The temporal resolution of 50 ms that is better than 100 ms of the requirement for ITER was achieved. We found that the temporal resolution is determined by a turbulent dispersion of the flow. The experiment for validation of the method determining the absolute D-T neutron flux was carried out by using the stainless steel (SS 316)/Water assembly to simulate the neutron field in the blanket region of ITER. The neutron emission rate measured with the water activation has a good agreement with that with the neutron yield monitor with associated α detector, and this technique shows the accuracy of the absolute neutron flux better than 10%. At the application on ITER-FEAT, the neutron activation with fluid flow has a dynamic range of 50 kW - 500 MW operation with a temporal resolution of 78 ms at the flow velocity of 10 m/s. (author)

  15. Supervision and technical coordination of the German activities in the 2D/3D-project

    International Nuclear Information System (INIS)

    Mayinger, F.

    1988-01-01

    The German Federal Minister for Research and Technology, the Japanese Atomic Energy Bureau, represented by the Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear Regulatory Commission (USNRC) made a contract to cooperate in the field of nuclear safety research with the aim to improve and to guarantee the safety of water-cooled nuclear reactors on an international basis by joint research activities in the 2D/3D-project. The necessity for these research activities results from gaps in the status of knowledge for a best-estimate analysis in emergency core cooling, from the legally established duty to minimize the radioactive emission to the environment as consequence of an incident, and from the effort to optimize the safeguard systems of nuclear reactors continuously and steadily. The activities which were performed in the frame of this project concentrated on the coordination of the experimental and theoretical work, as well as on the technical supervision with respect to an efficient attainment of the internationally aspired research aim and to an optimal adjustment with respect to the emergency core cooling problems of pressurized water reactors. (orig.) [de

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

    International Nuclear Information System (INIS)

    2000-01-01

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

  17. Report of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. Result evaluation in fiscal year 2000

    International Nuclear Information System (INIS)

    2001-06-01

    The Research Evaluation Committee, which consisted of 14 members from outside of the Japan Atomic Energy Research Institute (JAERI), set up an Ad Hoc Review Committee on Nuclear Safety Research in accordance with the Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations in order to evaluate the R and D accomplishments achieved for five years from Fiscal Year 1995 to Fiscal Year 1999 at Department of Reactor Safety Research, Department of Fuel Cycle Safety Research, Department of Environmental Safety Research and Department of Safety Research Technical Support in Tokai Research Establishment at JAERI. The Ad Hoc Review Committee consisted of 11 specialists from outside of JAERI. The Ad Hoc Review Committee conducted its activities from December 2000 to February 2001. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Ad Hoc Review Committee meeting which was held on December 11, 2000, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Ad Hoc Review Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on March 16, 2001. This report describes the result of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. (author)

  18. Report of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. Result evaluation in fiscal year 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-01

    The Research Evaluation Committee, which consisted of 14 members from outside of the Japan Atomic Energy Research Institute (JAERI), set up an Ad Hoc Review Committee on Nuclear Safety Research in accordance with the Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations in order to evaluate the R and D accomplishments achieved for five years from Fiscal Year 1995 to Fiscal Year 1999 at Department of Reactor Safety Research, Department of Fuel Cycle Safety Research, Department of Environmental Safety Research and Department of Safety Research Technical Support in Tokai Research Establishment at JAERI. The Ad Hoc Review Committee consisted of 11 specialists from outside of JAERI. The Ad Hoc Review Committee conducted its activities from December 2000 to February 2001. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Ad Hoc Review Committee meeting which was held on December 11, 2000, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Ad Hoc Review Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on March 16, 2001. This report describes the result of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. (author)

  19. Information management systems for integrating the technical data and regulatory requirements of environmental restoration activities

    International Nuclear Information System (INIS)

    Geffen, C.A.; Garrett, B.A.; Walter, M.B.

    1990-03-01

    Current environmental regulations require that comprehensive planning be conducted before remediating a hazardous waste site to characterize the nature and extent of site contamination, calculate the risk to the public, and assess the effectiveness of various remediation technologies. Remediation of Department of Energy (DOE) sites contaminated with hazardous or mixed wastes will require the effective integration of scientific and engineering data with regulatory and institutional requirements. The information management challenge presented by waste site cleanup activities goes beyond merely dealing with the large quantity of data that will be generated. The information must be stored, managed, and presented in a way that provides some consistency in approach across sites, avoids duplication of effort, and facilitates responses to requests for information from the regulators and the public. This paper provides background information on the regulatory requirements for data gathering and analysis for environmental restoration activities, and outlines the data and information management requirements for completing the pre-remediation phases of an environmental restoration project. Information management systems for integrating the regulatory and institutional requirements of the environmental restoration process with the technical data and analysis requirements are also described. 7 refs

  20. Active learning in the space engineering education at Technical University of Madrid

    Science.gov (United States)

    Rodríguez, Jacobo; Laverón-Simavilla, Ana; Lapuerta, Victoria; Ezquerro Navarro, Jose Miguel; Cordero-Gracia, Marta

    This work describes the innovative activities performed in the field of space education at the Technical University of Madrid (UPM), in collaboration with the center engaged by the European Space Agency (ESA) in Spain to support the operations for scientific experiments on board the International Space Station (E-USOC). These activities have been integrated along the last academic year of the Aerospatiale Engineering degree. A laboratory has been created, where the students have to validate and integrate the subsystems of a microsatellite by using demonstrator satellites. With the acquired skills, the students participate in a training process centered on Project Based Learning, where the students work in groups to perform the conceptual design of a space mission, being each student responsible for the design of a subsystem of the satellite and another one responsible of the mission design. In parallel, the students perform a training using a ground station, installed at the E-USOC building, which allow them to learn how to communicate with satellites, how to download telemetry and how to process the data. This also allows students to learn how the E-USOC works. Two surveys have been conducted to evaluate the impact of these techniques in the student engineering skills and to know the degree of satisfaction of students with respect to the use of these learning methodologies.

  1. 75 FR 55306 - Smart Grid Advisory Committee

    Science.gov (United States)

    2010-09-10

    ... accommodate Committee business. The final agenda will be posted on the Smart Grid Web site at http://www.nist.... The Committee shall provide input to NIST on the Smart Grid Standards, Priority, and Gaps. The... research and standards activities. 5. Upon request of the Director of NIST, the Committee will prepare...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-09-30

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

  3. Standing Concertation Committee

    CERN Multimedia

    2007-01-01

    Ordinary meeting on 30 January 2007 The main items discussed at the meeting of the Standing Concertation Committee on 30 January 2007 included: Administrative Circular No. 26: with the introduction of the merit recognition system in the framework of the 5-yearly review of CERN employment conditions, Administrative Circular No. 26 has been revised. The committee took note of the revised document which is being finalized for submission to the Director-General for approval in the near future. Technical analysis of CERN Health Insurance Scheme: the Committee was informed that a group has been set up by the Director-General to analyse the financial situation of the CERN Health Insurance Scheme in the short and long term, and to propose measures to ensure that the Scheme remains in financial balance, with adequate cover, over the medium term. The group's terms of reference and membership were communicated. Voluntary programmes It was announced that the programmes: 'part-time work as a pre-retirement measure...

  4. Standing Concertation Committee

    CERN Multimedia

    2007-01-01

    ORDINARY MEETING ON 30 JANUARY 2007 The main items discussed at the meeting of the Standing Concertation Committee on 30 January 2007 included: Administrative Circular No. 26: with the introduction of the merit recognition system in the framework of the 5-yearly review of CERN employment conditions, Administrative Circular No. 26 has been revised. The Committee took note of the revised document which is being finalized for submission to the Director-General for approval in the near future. Technical analysis of CERN Health Insurance Scheme: the Committee was informed that a group has been set up by the Director-General to analyse the financial situation of the CERN Health Insurance Scheme in the short and long term, and to propose measures to ensure that the Scheme remains in financial balance, with adequate cover, over the medium term. The group's terms of reference and membership were communicated. Voluntary programmes It was announced that the programmes: 'part-time work as a pre-retirement mea...

  5. Organizing Committee Advisory Committee 187

    Indian Academy of Sciences (India)

    Organizing Committee. V M Datar (Chairman). Bhabha Atomic Research Centre, Mumbai, India. D C Biswas (Convener). Bhabha Atomic Research Centre, Mumbai, India. K Mahata (Secretary). Bhabha Atomic Research Centre, Mumbai, India. Z Ahmed. Bhabha Atomic Research Centre, Mumbai, India. P V Bhagwat.

  6. Impact of new environmental and safety regulations on uranium exploration, mining, milling and management of its waste. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    Concern for health, safety and the environment has grown rapidly during the last two decades. Exploitation of any mineral commodity, including uranium, involves the modification of the surrounding environment. Appropriate regulations governing such activities can assure good practices and minimize possible negative impacts on the environment and the health and safety of the workers and the general public. During the past few years, a number of countries have promulgated new regulations related to uranium exploitation, mining, milling and the related waste management. Recent regulations are stricter in terms of environmental assessment, mitigation, radiation protection and control of waste. The impact of those regulations in developed countries has resulted in better planning of operations, improvement in mine and mill designs and a more efficient approach to tailings management. The Meeting was attended by 25 participants from 17 countries representing government organizations and private industry. This document includes 21 papers presented at the Meeting on new experiences in major uranium producing countries on the subject, past producers, as well as on country where regulations and related regulatory structure are still at the early evolutionary stage. Each of the papers was indexed separately.

  7. Impact of new environmental and safety regulations on uranium exploration, mining, milling and management of its waste. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-09-01

    Concern for health, safety and the environment has grown rapidly during the last two decades. Exploitation of any mineral commodity, including uranium, involves the modification of the surrounding environment. Appropriate regulations governing such activities can assure good practices and minimize possible negative impacts on the environment and the health and safety of the workers and the general public. During the past few years, a number of countries have promulgated new regulations related to uranium exploitation, mining, milling and the related waste management. Recent regulations are stricter in terms of environmental assessment, mitigation, radiation protection and control of waste. The impact of those regulations in developed countries has resulted in better planning of operations, improvement in mine and mill designs and a more efficient approach to tailings management. The Meeting was attended by 25 participants from 17 countries representing government organizations and private industry. This document includes 21 papers presented at the Meeting on new experiences in major uranium producing countries on the subject, past producers, as well as on country where regulations and related regulatory structure are still at the early evolutionary stage. Each of the papers was indexed separately

  8. A smoothed particle hydrodynamics (SPH) study on polydisperse sediment from technical activities on seabed

    Science.gov (United States)

    Tran-Duc, Thien; Phan-Thien, Nhan; Khoo, Boo Cheong

    2018-02-01

    Technical activities to collect poly-metallic nodules on a seabed are likely to disturb the top-layer sediment and re-suspend it into the ambient ocean water. The transport of the re-suspended polydisperse-sized sediment is a process in which particles' size variation leads to a difference in their settling velocities; and thus the polydispersity in sizes of sediment has to be taken into account in the modeling process. The sediment transport within a window of 12 km is simulated and analyzed numerically in this study. The sediment characteristic and the ocean current data taken from the Peru Basin, Pacific Ocean, are used in the simulations. More than 50% of the re-suspended sediment are found to return to the bottom after 24 h. The sediment concentration in the ambient ocean water does not exceed 3.5 kg/m3 during the observed period. The deposition rate steadily increases and reaches 70% of the sediment re-suspension rate after 24 h. The sediment plume created by the activities comprises mainly very fine sediment particles (clays and silts), whereas coarser particles (sands) are found in abundance in the deposited sediment within 1 km from the source location. It is also found that the deposition process of the re-suspended sediment is changed remarkably as the current velocity increases from 0.05 m/s (medium current) to 0.1 m/s (strong current). The strong sediment deposition trend is also observed as the sediment source moves continuously over a region due to the sediment scattering effect.

  9. Activity of Ethics Committees in Europe on issues related to clinical trials in paediatrics: Results of a survey

    Czech Academy of Sciences Publication Activity Database

    Altavilla, A.; Giaquinto, C.; Giocanti, D.; Manfredi, C.; Aboulker, J.-P.; Bartoloni, F.; Cattani, E.; Giudice, M. L.; Mellado Peňa, M.J.; Nagler, R.; Peterson, C.; Vajnerová, Olga; Bonifazi, F.; Ceci, A.

    2009-01-01

    Roč. 11, 1-2 (2009), s. 79-87 ISSN 1389-2827 Grant - others:EC(XE) LSHBCT-2005-005126 Institutional research plan: CEZ:AV0Z50110509 Keywords : ethic committees * clinical trials * pediatrics Subject RIV: FP - Other Medical Disciplines

  10. Improving of technical characteristics of launch vehicles with liquid rocket engines using active onboard de-orbiting systems

    Science.gov (United States)

    Trushlyakov, V.; Shatrov, Ya.

    2017-09-01

    In this paper, the analysis of technical requirements (TR) for the development of modern space launch vehicles (LV) with main liquid rocket engines (LRE) is fulfilled in relation to the anthropogenic impact decreasing. Factual technical characteristics on the example of a promising type of rocket ;Soyuz-2.1.v.; are analyzed. Meeting the TR in relation to anthropogenic impact decrease based on the conventional design approach and the content of the onboard system does not prove to be efficient and leads to depreciation of the initial technical characteristics obtained at the first design stage if these requirements are not included. In this concern, it is shown that the implementation of additional active onboard de-orbiting system (AODS) of worked-off stages (WS) into the onboard LV stages systems allows to meet the TR related to the LV environmental characteristics, including fire-explosion safety. In some cases, the orbital payload mass increases.

  11. MHD Technology Transfer, Integration and Review Committee. Seventh semi-annual status report, April 1991--September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    This seventh semi-annual status report of the MHD Technology Transfer, Integration and Review Committee (TTIRC) summarizes activities of the TTIRC during the period April 1991 through September 1991. It includes a summary and minutes of the General Committee meeting, progress summaries of ongoing POC contracts, discussions pertaining to technical integration issues in the POC program, and planned activities for the next six months. The meeting included test plan with Western coal, seed regeneration economics, power management for the integrated topping cycle and status of the Clean Coal Technology Proposal activities. Appendices cover CDIF operations HRSR development, CFFF operations etc.

  12. Spent fuel storage facility at science and technical center 'Sosny': Experience of ten years activity

    International Nuclear Information System (INIS)

    Chigrinov, S.; Goulo, V.; Lunev, A.; Belousov, N.; Salnikov, L.; Boiko, L.

    2000-01-01

    Spent fuel storage of the Academic Science and Technical Center in Minsk is in operation already more then 10 years. In the paper aspects of its design, operation practice, problems and decisions for future are discussed. (author)

  13. An evaluation of knowledge, attitude, and practice of institutional ethics committee members from eastern India regarding ethics committee functioning and pharmacovigilance activities conducted during clinical trials: A pilot study

    Directory of Open Access Journals (Sweden)

    Subhrojyoti Bhowmick

    2014-01-01

    Full Text Available Purpose of study: The vital responsibility of Institutional Ethics Committee (IEC members is to ensure the safety of the subjects participating in clinical trials. Hence, it is essential for IEC members to be aware of the common pharmacovigilance strategies followed during clinical trials. However, the information about the knowledge, attitude, and practice of IEC members regarding the pharmacovigilance activities followed during clinical trials is scarce worldwide, especially in India. Hence, this cross-sectional study was designed to assess the knowledge, attitude, and practice of IEC members of 10 hospitals of Kolkata, India. Materials and Methods: A cross-sectional study using a self-administered, validated questionnaire was conducted among 10 hospitals (five government and five corporate hospitals in Kolkata conducting active clinical research and having functional Ethics Committees (ECs in the month of September-November, 2012. An IEC approval was taken for this study. Two reminders were given to all EC members through telephone/e-mail for completion and returning of the forms. The filled in forms were returned to their respective Member Secretaries, from whom authors′ collected the forms. Data were analyzed using SPSS version 16.0 software and MS-Excel 2007. Categorical data were analyzed using Chi-square test and a P < 0.05 was considered statistically significant. Results: Out of the 100 distributed questionnaires, 40 were returned of which 10 were not filled properly. Overall awareness regarding different pharmacovigilance terminologies and activities among EC members from nonmedical background (71.43% was found to be more than that of the medical members (68.75%, though the figure was not statistically significant. Majority of the members (75% felt that EC should decide compensation in case of a serious adverse event. Conclusion: The present study signifies that there is a low level of awareness in IEC members of Kolkata regarding

  14. Vadose zone microbial community structure and activity in metal/radionuclide contaminated sediments. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Balkwill, David L.

    2002-08-17

    This final technical report describes the research carried out during the final two months of the no-cost extension ending 11/14/01. The primary goals of the project were (1) to determine the potential for transformation of Cr(VI) (oxidized, mobile) to Cr(III) (reduced, immobile) under unsaturated conditions as a function of different levels and combinations of (a) chromium, (b) nitrate (co-disposed with Cr), and (c) molasses (inexpensive bioremediation substrate), and (2) to determine population structure and activity in experimental treatments by characterization of the microbial community by signature biomarker analysis and by RT-PCR and terminal restriction fragment length polymorphism (T-RFLP) and 16S ribosomal RNA genes. It was determined early in the one-year no-cost extension period that the T-RFLP approach was problematic in regard to providing information on the identities of microorganisms in the samples examined. As a result, it could not provide the detailed information on microbial community structure that was needed to assess the effects of treatments with chromium, nitrate, and/or molasses. Therefore, we decided to obtain the desired information by amplifying (using TR-PCR, with the same primers used for T-RFLP) and cloning 16S rRNA gene sequences from the same RNA extracts that were used for T-RFLP analysis. We also decided to use a restriction enzyme digest procedure (fingerprinting procedure) to place the clones into types. The primary focus of the research carried out during this report period was twofold: (a) to complete the sequencing of the clones, and (b) to analyze the clone sequences phylogenetically in order to determine the relatedness of the bacteria detected in the samples to each other and to previously described genera and species.

  15. Review of occupational safety and health activities in Southern Africa funded under the DANIDA/ILO framework agreement on technical cooperation

    DEFF Research Database (Denmark)

    Hasle, Peter; Jørgensen, Claus

    2003-01-01

    A review of occupational safety and health activities in Southern Africa (SADC region) which have been funded under the DANIDA/ILO framework agreement on technical cooperation.......A review of occupational safety and health activities in Southern Africa (SADC region) which have been funded under the DANIDA/ILO framework agreement on technical cooperation....

  16. Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

    International Nuclear Information System (INIS)

    Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

    1985-05-01

    Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented

  17. Report on the activities of the ASME-NQA Committee Working Group on Quality Assurance Requirements for Research and Development, April 1990 to August 1991

    Energy Technology Data Exchange (ETDEWEB)

    Dronkers, J.J.

    1991-09-01

    This report transmits to the public eye the activities of the American Society of Mechanical Engineers-Nuclear Quality Assurance (ASME-NQA) Committee Working Group on Quality Assurance Requirements for Research and Development. The appendix lists the members of this group as of August 1991. The report covers a period of 17 months. The working group met eight times in this period, and much intellectual ground was traversed. There was seldom agreement on the nature of the task, but there was no doubt as to its urgency. The task was how to adapt the nuclear quality assurance standard, the NQA-1, to research and development work. 1 fig., 7 tabs.

  18. Waste management assessment and technical review programme. WATRP. An international peer review service for radioactive waste management activities

    International Nuclear Information System (INIS)

    1994-09-01

    International Atomic Energy Agency provides international peer review services in radioactive waste management to those Member States that have established radioactive waste management programmes. Such services are provided within Waste Management Assessment and Technical Review Programme (WATRP). The main objective of WATRP is to provide international expertise and information on a requested subject in the field of radioactive waste management and to validate that programmes and activities are sound and performing well. Refs, figs and tabs

  19. Goals, tasks and aspects of activity of Ukrainian State Scientific and Technical Center on Nuclear and Radiation Safety

    International Nuclear Information System (INIS)

    Kovbasenko, Yu.

    2001-01-01

    The goal of SSTC NRS activities is scientific, technical, analytical and expert support to the Nuclear Regulatory Department as a State Nuclear and Radiation Safety Regulatory Authority.The main tasks are: 1. Development and improvement of normative and legal framework in the field of nuclear power use in Ukraine; 2. Expert support in making regulatory decisions; 3. Research and development work on improvement engineering and operational safety of nuclear power facilities in Ukraine. The organizational structure of SSTC NRS is also given

  20. [Evaluation of the lifestyle of students of physiotherapy and technical & computer science basing on their diet and physical activity].

    Science.gov (United States)

    Medrela-Kuder, Ewa

    2011-01-01

    The aim of the study was the evaluation of a dietary habits profile and physical activity of Physiotherapy and Technical & Computer Science students. The research involved a group of 174 non-full-time students of higher education institutions in Krakow aged between 22 and 27. 81 students of the surveyed studied Physiotherapy at the University of Physical Education, whereas 93 followed a course in Technical & Computer Science at the Pedagogical University. In this project a diagnostic survey method was used. The study revealed that the lifestyle of university youth left much to be desired. Dietary errors were exemplified by irregular meals intake, low consumption of fish, milk and dairy, snacking between meals on high calorie products with a poor nutrient content. With regard to physical activity, Physiotherapy students were characterised by more positive attitudes than those from Technical & Computer Science. Such physical activity forms as swimming, team sports, cycling and strolling were declared by the surveyed the most frequently. Health-oriented education should be introduced in such a way as to improve the knowledge pertaining to a health-promoting lifestyle as a means of prevention of numerous diseases.