WorldWideScience

Sample records for technical options committee

  1. 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

  2. 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'

  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. 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.

  6. 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

  7. 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

  8. 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.

  9. 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.

  10. 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.

  11. 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...

  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. 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...

  2. 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...

  3. 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

  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. 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)

  17. 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...

  18. Technical note An investigation of the franchising option for water ...

    African Journals Online (AJOL)

    Technical note An investigation of the franchising option for water services operation ... of water services, and outlines the need to formulate a franchise model that ... made available to emerging entrepreneurs as the basis of a viable business.

  19. 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

  20. 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...

  1. Solar energy options: Technical economic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Visentin, R

    1982-01-01

    A general system approach on the earth suggests the conversion and distribution of solar energy as electricity, gas, solid and liquid fuels; the historical trend in energy management techniques is in favour of this hard technical proposal, because experience there exists on methods of transmission or transportation of previous kinds of energy vectors mentioned, and small changes in lifestyles toward energy conservation have to be considered in the final uses of the energy. Less hard system technologies will permit direct heat and electricity production close to the channels of energy consumptions; these systems will function as energy savers and their full exploitation implies greater impacts on energy use and lifestyles. As a general trend for government policies as well as for public decision impact on the social decision process, the proliferation of solar systems would permit to produce energy for the 'flowing energetic consumptions' (civil, transportation, agriculture, telecommunications, lighting, etc.) while the not renewable fuels could be properly invested in the production of strategic or durable materials; in this scheme the role of renewable resources is well defined to stabilize the whole civil system in which we are at present organized.

  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 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...

  7. 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...

  8. 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.)

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  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. 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.

  4. 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...

  5. 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...

  6. 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...

  7. 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...

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

    Energy Technology Data Exchange (ETDEWEB)

    Loew, Gregory

    2003-02-21

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

  9. 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

  10. 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...

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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.

  10. Technical options for the remediation of contaminated groundwater

    Energy Technology Data Exchange (ETDEWEB)

    1999-06-01

    This report provides a description of the nature and extent of problems related to radioactive groundwater contamination by outlining the environmental impacts, the sources of contamination and the contaminants of concern radionuclides and their associated contaminants - the main exposure pathways and transport processes and the assessment of risks associated with contaminated groundwater. The main emphasis of this report is on methodologies used in groundwater remediation and available technologies. The methodology section outlines the importance of an initial scoping analysis including the evaluation of uncertainties of the available data and the necessity for defining clear objectives for data collection. This is then followed by comprehensive site characterization, setting of goals and developing alternatives which will be analysed in detail. Available technologies are grouped generally into in situ methods aiming at a containment of the contaminants in place and engineered treatment methods involving an alteration of groundwater flow, quantity and/or quality to achieve compliance with set goals. Groundwater remediation by natural flushing allows the natural groundwater movement and geochemical processes to decrease the contaminant concentrations to acceptable levels over a specified period of time. This method is increasingly accepted in areas where the use of groundwater can be temporarily restricted or engineered cleanup methods do not offer particular advantage over the natural processes. The application of technological methods for remediating contaminated groundwaters has to be considered in conjunction with management options such as diversion and development of alternative water sources. The experience with groundwater contamination accrued in IAEA Member States is concentrated in those countries with active uranium mining and milling facilities and nuclear energy programmes. This experience is reported in the Annexes, which include case studies. It

  11. Technical options for the remediation of contaminated groundwater

    International Nuclear Information System (INIS)

    1999-06-01

    This report provides a description of the nature and extent of problems related to radioactive groundwater contamination by outlining the environmental impacts, the sources of contamination and the contaminants of concern radionuclides and their associated contaminants - the main exposure pathways and transport processes and the assessment of risks associated with contaminated groundwater. The main emphasis of this report is on methodologies used in groundwater remediation and available technologies. The methodology section outlines the importance of an initial scoping analysis including the evaluation of uncertainties of the available data and the necessity for defining clear objectives for data collection. This is then followed by comprehensive site characterization, setting of goals and developing alternatives which will be analysed in detail. Available technologies are grouped generally into in situ methods aiming at a containment of the contaminants in place and engineered treatment methods involving an alteration of groundwater flow, quantity and/or quality to achieve compliance with set goals. Groundwater remediation by natural flushing allows the natural groundwater movement and geochemical processes to decrease the contaminant concentrations to acceptable levels over a specified period of time. This method is increasingly accepted in areas where the use of groundwater can be temporarily restricted or engineered cleanup methods do not offer particular advantage over the natural processes. The application of technological methods for remediating contaminated groundwaters has to be considered in conjunction with management options such as diversion and development of alternative water sources. The experience with groundwater contamination accrued in IAEA Member States is concentrated in those countries with active uranium mining and milling facilities and nuclear energy programmes. This experience is reported in the Annexes, which include case studies. It

  12. 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...

  13. 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.)

  14. 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

  15. 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...

  16. 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

  17. 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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

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

    Science.gov (United States)

    2011-10-19

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

  20. 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…

  1. 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...

  2. Technical Assessments of Future European Space Transportation Options

    OpenAIRE

    Sippel, Martin; van Foreest, Arnold; Dutheil, Jean-Philippe; Philip, Peter

    2007-01-01

    The paper describes some of the most recent activities in Germany in the technical assessment of future European launcher architecture. In focus is a joint effort of DLR-SART with German launcher industry in the definition of a next generation upper-medium class expendable TSTO with an initial operational capability after 2020. Involved companies are EADS astrium and MT Aerospace. This DLR-agency funded study WOTAN investigates fully cryogenic launchers as well as those with a com...

  3. The $2000 Electric Powertrain Option-1 Program. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    This report describes the tasks accomplished as part of Northrop Grumman's TRP $2000 Electric Powertrain Option-1 program. Northrop Grumman has strived to achieve technology advances and development considered as high priority to the success of future electric vehicles. Northrop Grumman has achieved the intent of the program by taking several steps toward reducing the cost of the electric vehicle powertrain, demonstrating technologies in the form of hardware and introducing enhancements into production that are consistent with the needs of the market.

  4. 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

  5. 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)

  6. 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

  7. 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.

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

    International Nuclear Information System (INIS)

    2001-05-01

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

  9. 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

  10. 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…

  11. 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...

  12. 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...

  13. 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...

  14. 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...

  15. 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

  16. 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...

  17. 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

  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. An investigation of dematerialization planning options at tourism destinations: Technical and behavioural dimensions

    OpenAIRE

    Kelly, Joseph

    2006-01-01

    The goal of this dissertation is to develop a conceptual framework and associated methods for evaluating alternative tourism planning strategies in terms of dematerialization and acceptability amongst tourists. Its objectives are to (1) examine the technical potential of dematerialization planning options in tourism destinations, (2) investigate tourist perspectives concerning destination planning alternatives that promote dematerialization, (3) assess the travel market responses and demateri...

  20. 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.

  1. Technical and economic evaluation of controlled disposal options for very low level radioactive wastes

    International Nuclear Information System (INIS)

    Robinson, P.J.; Vance, J.N.

    1990-08-01

    Over the past several years, there has been considerable interest by the nuclear industry in the Nuclear Regulatory Commission (NRC) explicitly defined an activity level in plant waste materials at which the radiological impacts would be so low as to be considered Below Regulatory Concern (BRC). In January 1989, Electric Power Research Institute (EPRI) completed an extensive industry research effort to develop the technical bases for establishing criteria for the disposal of very low activity wastes in ordinary disposal facilities. The Nuclear Management and Resources Council (NUMARC), with assistance from the Edison Electric Institute (EEI) and the Electric Power Research Institute (EPRI), drafted a petition titled: ''Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Radioactive Wastes from Commercial Nuclear Power Plants.'' Subsequent to the industry making a final decision for submittal of the drafted BRC petition, EPRI was requested to evaluate the technical and economic impact of six BRC options. These options are: take no action in pursuing a BRC waste exemption, petition the NRC for authorization to disposal of any BRC waste in any ordinary disposal facility, limit disposal of BRC waste to the nuclear power plant site, limit disposal of BRC waste to the nuclear power plant site and other utility owned property, petition for a mixed waste exemption, and petition for single waste stream exemptions in sequence (i.e. soil, followed by sewage sludge, etc.). The petition and technical bases were written to support the disposal of any BRC waste type in any ordinary disposal facility. These documents do not provide all of the technical and economic information needed to completely assessment the BRC options. This report provides the technical and economic basis for a range of options concerning disposal of very low activity wastes. 3 figs., 20 tabs

  2. 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

  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. 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

  6. 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

  7. 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.

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

    International Nuclear Information System (INIS)

    1997-11-01

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

  9. Republic of the Marshall Islands. Energy Project Development Options and Technical Assessment (2013)

    Energy Technology Data Exchange (ETDEWEB)

    Conrad, Misty Dawn [National Renewable Energy Lab. (NREL), Golden, CO (United States); Olis, Dan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ness, J. Erik [National Renewable Energy Lab. (NREL), Golden, CO (United States); Esterly, Sean [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2015-09-01

    The advancement of renewable energy and energy efficient technologies continues to be fluid. There are many technical opportunities and strategies that can be utilized to guide communities to deploy cost-effective commercial alternative energy options; however, to achieve aggressive economic, environmental, and security goals, it requires a comprehensive, integrated approach. This document reports on the initial findings of an energy assessment that was conducted for the Republic of the Marshall Islands.

  10. The future is yours--Get ready! Career options in scientific and technical fields. Revision

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This 50 page brochure was developed by Brookhaven National Laboratory to encourage high school students to begin considering careers in the scientific and technical fields. The topics of the brochure include career selection, career options, a review of training required for each occupation, a collection of profiles of BNL employees describing how they chose and prepared for their careers, a description of BNL educational programs for high school students, and profiles of some of the students participating in these programs.

  11. 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

  12. 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)

  13. 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.

  14. 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

  15. Review of scientific and technical options for the Superconducting Super Collider Program

    Energy Technology Data Exchange (ETDEWEB)

    Dombeck, T.

    1993-11-01

    This document is a review of options for the Superconducting Super Collider (SSC) Program. It is the result of an informal study by an ad-hoc working group consisting of Laboratory physicists and engineers who investigated the physics and technical implications of a number of possible alternative SSC programs. Previous studies have shown, and early in this study it was confirmed, that a collider of approximately 20 TeV protons on 20 TeV protons with a luminosity of 10{sup 33} cm{sup {minus}2}s{sup {minus}1} at each interaction region is needed to support a physics program that is guaranteed to answer existing particle physics questions and make new discoveries. Therefore, all options considered in this document were consistent with attainment of these original goals for the SSC. One promising option considered was a program of colliding anti-protons on protons as a possible means to reduce the cost of the SSC by eliminating one of the Collider rings. However, the luminosity requirements to obtain the SSC physics goals remains the same as for protons colliding with protons and this study confirms that even though progress has been made over the last ten years in obtaining the high intensity anti-proton beams necessary, a luminosity higher than 10{sup 32} cannot be guaranteed. Other options were examined to see what advantages could be derived by departing from the SSC baseline program, either in schedule, in parameters, by staging, or by combinations of these options. Even though we considered re-examination of the cost of the baseline program to be beyond the scope of this document, differential cost savings were estimated. Finally, a brief survey of progress over the last ten years in various technical areas that might lead to more cost effective engineering designs was included in this study, such as higher magnetic field magnets resulting from lower operating temperatures or higher current-carrying superconducting materials.

  16. Review of scientific and technical options for the Superconducting Super Collider Program

    International Nuclear Information System (INIS)

    Dombeck, T.

    1993-11-01

    This document is a review of options for the Superconducting Super Collider (SSC) Program. It is the result of an informal study by an ad-hoc working group consisting of Laboratory physicists and engineers who investigated the physics and technical implications of a number of possible alternative SSC programs. Previous studies have shown, and early in this study it was confirmed, that a collider of approximately 20 TeV protons on 20 TeV protons with a luminosity of 10 33 cm -2 s -1 at each interaction region is needed to support a physics program that is guaranteed to answer existing particle physics questions and make new discoveries. Therefore, all options considered in this document were consistent with attainment of these original goals for the SSC. One promising option considered was a program of colliding anti-protons on protons as a possible means to reduce the cost of the SSC by eliminating one of the Collider rings. However, the luminosity requirements to obtain the SSC physics goals remains the same as for protons colliding with protons and this study confirms that even though progress has been made over the last ten years in obtaining the high intensity anti-proton beams necessary, a luminosity higher than 10 32 cannot be guaranteed. Other options were examined to see what advantages could be derived by departing from the SSC baseline program, either in schedule, in parameters, by staging, or by combinations of these options. Even though we considered re-examination of the cost of the baseline program to be beyond the scope of this document, differential cost savings were estimated. Finally, a brief survey of progress over the last ten years in various technical areas that might lead to more cost effective engineering designs was included in this study, such as higher magnetic field magnets resulting from lower operating temperatures or higher current-carrying superconducting materials

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-01

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

  18. 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

  19. 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

  20. 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...

  1. 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)

  2. 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.

  3. 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.

  4. 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)

  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. 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

  7. 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

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

    International Nuclear Information System (INIS)

    1996-09-01

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

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

    International Nuclear Information System (INIS)

    1997-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

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

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

    International Nuclear Information System (INIS)

    1996-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

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

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

    Science.gov (United States)

    2010-05-03

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

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

  15. Status of feasibility study for various technical options of FBR systems

    International Nuclear Information System (INIS)

    Kani, Yoshio

    2000-01-01

    JNC (Japan Nuclear Cycle Development Institute) has started a new research project of feasibility studies (F/S) for a wide variety option of fast breeder reactor (FBR) and related fuel cycle in order to develop an economically competitive FBR cycle system fro commercialization. JNC and the electric untilities in Japan have established a new organization in JNC to perform the F/S since July 1, 1999. The organization has undertaken feasibility studies (F/S) in order to determine promising FBR cycle concepts and define necessary RandD tasks. The long-term targets of commercialized FBR cycle system are set as ensuring safety, economic competitiveness relative to future LWRs, efficient utilization of resources, reduction in environmental burden, and enhancement of nuclear non-proliferation. This paper describes the progress of design studies for a wide variety of technical options of FBR plants in the framework of the F/S. We make efforts towards considering all key issues so as not to fail to notice the best concept in a commercialized stage. In the study of technical options, the identified coolant types are sodium, heavy metal (lead and lead-bismuth), gas (carbon dioxide and helium ) and water (boiling water, pressurized water and supercritical water). The classified types of fuel are mixed oxide, nitride and metal. Design studies of small size modular plant concepts are also performed. We study many reactor concepts in combination with a coolant type and a fuel type, understand characteristics of each reactor concept based on our experience and an extensive survey of literature, and make a draft design of each reactor concept for rough estimation of construction costs. We also check how far the concept accomplishes each index (safety, economy, resource utilization, etc.) of design requirements, and will select several promising reactor concepts. (author)

  16. 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

  17. Regulations of 19 August 1978 on the optional principles of the Nuclear Safety Committee

    International Nuclear Information System (INIS)

    1978-01-01

    These regulations were published in the Turkish Official Gazette of 19 August 1978 and were made pursuant to Decree no. 7/9141 of 1975 on licensing of nuclear installations which established the Nuclear Safety Committee. They determine the duties and responsibilities of the Committee, its qualifications, its operating principles and its relations with the Nuclear Safety Assistance Service set up in the Turkish Atomic Energy Commission for the purposes of assisting its Secretary General. The regulations also lay down the procedures to be applied for consultations on granting licences. (NEA) [fr

  18. 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.

  19. A review of technical options for solar charging stations in Asia and Africa

    Directory of Open Access Journals (Sweden)

    R. H. Almeida

    2015-09-01

    Full Text Available Charging stations are an attractive solution to provide access to electricity to low income populations with low energy consumption in remote and off-grid areas. This paper reviews the state of the art of charging stations, with special focus on the technical options. Forty-five different actors in this field were analysed, based on academic publications, reports, online search and surveys. Results show that most stations are run in Sub Saharan Africa and South Asia, are powered by solar energy and although there are many different energy services targeted, the most popular services are charging batteries, mobile phones and lamps. The first charging station was installed in 1992 but most activities happen after 2005. This recent growth has been enabled by the falling cost of photovoltaic modules, learning effect, economies of scale, financial innovation, private sector involvement and worldwide dissemination of mobile phones. While in the first system the only purpose was to charge solar photovoltaic lanterns, the first multi-purpose station appeared in 2008. As expected, the technical challenges are mostly related to the use of batteries not only because they represent the component with shortest lifetime but also because if the battery is not for individual use, social questions arise due to poor definition of rights and duties of the customers. Furthermore, the development of a sustainable business model is also a challenge since this requires technical skills and system monitoring that are not usually available locally. Finally, it is also suggested that the minimum technical quality standards for charging stations should be defined and implemented.

  20. 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.

  1. 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

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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.)

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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.)

  13. 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

  14. 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

  15. 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.

  16. K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

    International Nuclear Information System (INIS)

    Beary, M.M.; Honekemp, J.R.; Winters, N.

    1995-01-01

    Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE's commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path

  17. K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

    Energy Technology Data Exchange (ETDEWEB)

    Beary, M.M.; Honekemp, J.R.; Winters, N. [Science Applications International Corp., Richland, WA (United States)

    1995-01-01

    Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE`s commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path.

  18. 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

  19. 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)

  20. 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...

  1. 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...

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

    International Nuclear Information System (INIS)

    2004-02-01

    low cost options, and increasing plant survival after propagation, bioreactors, and outreach of material to the growers and farmers in developing countries. Bioreactors in plant propagation can produce millions of plants and may cut down the cost of plant production, which is yet not commonly used in developing countries. However, in the near future it could be well integrated into large scale commercial micropropagation in both developed and developing countries. In all cases, such options must be integrated without reducing the efficiency of plant propagation and compromising the plant quality. This TECDOC was prepared on the basis of contributions made by the participants in the Technical Meeting on Low Cost Tissue Culture Technology for Developing Countries, Vienna, 26-30 August 2002. This publication should be of great value to plant propagators, managers of tissue culture laboratories, scientists, organizations contemplating the establishment of new laboratories, and ongoing commercial concerns, all of whom may wish to incorporate low cost options into their day-to-day operations. Also, it would greatly serve plant propagation enterprises in developing countries with scarce funds and poor infrastructure for sustainable food production. Many of the options described can also be integrated in tissue culture laboratories that use mutation induction to develop new mutant varieties of both vegetatively and seed propagated plants, and for rapid release of the selected mutants

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-02-01

    low cost options, and increasing plant survival after propagation, bioreactors, and outreach of material to the growers and farmers in developing countries. Bioreactors in plant propagation can produce millions of plants and may cut down the cost of plant production, which is yet not commonly used in developing countries. However, in the near future it could be well integrated into large scale commercial micropropagation in both developed and developing countries. In all cases, such options must be integrated without reducing the efficiency of plant propagation and compromising the plant quality. This TECDOC was prepared on the basis of contributions made by the participants in the Technical Meeting on Low Cost Tissue Culture Technology for Developing Countries, Vienna, 26-30 August 2002. This publication should be of great value to plant propagators, managers of tissue culture laboratories, scientists, organizations contemplating the establishment of new laboratories, and ongoing commercial concerns, all of whom may wish to incorporate low cost options into their day-to-day operations. Also, it would greatly serve plant propagation enterprises in developing countries with scarce funds and poor infrastructure for sustainable food production. Many of the options described can also be integrated in tissue culture laboratories that use mutation induction to develop new mutant varieties of both vegetatively and seed propagated plants, and for rapid release of the selected mutants.

  4. 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

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

    International Nuclear Information System (INIS)

    1997-11-01

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

  6. 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

  7. 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

  8. 41th Plenary Meeting Report of the Scientific, Technical and Economic Committee for Fisheries (PLEN-12-03)

    DEFF Research Database (Denmark)

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

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

  9. 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...

  10. Technical/ administrative options for managing tritium MCL exceedances in P-area groundwater and Steel Creek

    Energy Technology Data Exchange (ETDEWEB)

    Ross, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-04-01

    This white paper was requested by the Core Team (United States Department of Energy [USDOE], United States Environmental Protection Agency [USEPA], and South Carolina Department of Health and Environmental Control [SCDHEC]) at the P-Area Groundwater (PAGW) Operable Unit (OU) Scoping Meeting held in January 2017 to discuss recent data and potential alternatives in support of a focused Corrective Measures Study/Feasibility Study (CMS/FS). This white paper presents an overview of the problem, and a range of technical and administrative options for addressing the tritium contamination in groundwater and Steel Creek. As tritium cannot be treated practicably, alternatives are limited to media transfer, containment and natural attenuation principally relying on radioactive decay. Using other groundwater OU decisions involving tritium as precedent, Savannah River Nuclear Solutions (SRNS) recommends that final tritium alternatives be evaluated in a CMS/FS, understanding that the likely preferred remedy will include natural attenuation with land use controls (LUCs). This is based on the inability to significantly reduce tritium impact to Steel Creek using an engineered solution as compared to natural attenuation. The timing of this evaluation could be conducted concurrently with the final remedy evaluation for volatile organic compounds (VOCs).

  11. Double row spacing and drip irrigation as technical options in energy sorghum management

    Directory of Open Access Journals (Sweden)

    Neri Roncucci

    2014-02-01

    Full Text Available The effect of two row spacing configurations and four water supply levels was investigated on sweet and fibre sorghum in Central Italy for two consecutive years. Results highlighted the influence of both irrigation and row spatial configuration on crop productivity. Indeed, several studies have pointed out the positive response of sorghum to irrigation in Mediterranean climate, as in this environment water stress represents one of the main limiting factors on crop productivity. On the other hand, few attempts have been made to explore the role of row spacing on energy sorghum productivity. Results outlined an average increase in sorghum dry biomass yield ranging from +23% to +79% at variable rates of water supply as compared to rainfed control. The positive effect of irrigation was also observed on leaf area index and radiation use efficiency. Moreover, we observed a crop yield increase, from 9% to 20%, under double row spacing compared to the standard planting pattern (i.e. single row spacing. Finally, it was confirmed the efficient use of water by sorghum and the great ability of sorghum to increase its biomass yield in response to increasing volumes of water supplied. Therefore, this work suggests how row spacing configuration and drip irrigation could be feasible technical options to increase sorghum biomass yields in Mediterranean environments. These techniques should be experienced by farmers towards a sustainable intensification of current cropping systems.

  12. Homeless Mentally Ill: Problems and Options in Estimating Numbers and Trends. Report to the Chairman, Committee on Labor and Human Resources, U.S. Senate.

    Science.gov (United States)

    General Accounting Office, Washington, DC. Program Evaluation and Methodology Div.

    In response to a request by the United States Senate Committee on Labor and Human Resources, the General Accounting Office (GAO) examined the methodological soundness of current population estimates of the number of homeless chronically mentally ill persons, and proposed several options for estimating the size of this population. The GAO reviewed…

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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...

  3. 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....

  4. [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.

  5. 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

  6. 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

  7. 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...

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. Assessment of the technical viability of reactor options for plutonium disposition

    International Nuclear Information System (INIS)

    Primm, R.T. III.

    1996-01-01

    Various reactor concepts for the disposition of surplus Pu have been proposed by reactor vendors; not all have attained the same level of technical viability. Studies were performed to differentiate between reactor concepts by devising a quantitative index for technical viability. For a quantitative assessment, three issues required resolution: the definition of a technical maturity scale, the treatment of ''subjective'' factors which cannot be easily represented in a quantitative format, and the protocol for producing a single technical viability figure-of-merit for each alternative. Alternatives involving the use of foreign facilities were found to be the most technically viable

  14. 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

  15. Risk perception of various technical options in the field of radioactive waste management

    International Nuclear Information System (INIS)

    Cameron, F.X.

    1996-01-01

    The author's group had a wide ranging discussion of risk and, at the very end of the discussion got to the question that was posed to them, which is that of risk perception of various technical options in the field of radioactive waste management. Some of the points that were made in this discussion is a reality that the group, as decision-makers, have to deal with, and it has to be treated as a reality. Secondly, the scientist looks at risk from the classic definition of ''probability times consequences'', but the public only looks at the consequences side of the equation, and too often the probability of something happening is treated as a probability of one that it will actually happen. A third problem that was identified in this area is that often the efforts to make the disposal of waste safer may contribute, in the public mind, to the fact that the risk is even more hazardous. And the last problem is that people do not trust what a decision maker is saying when he talks about the fact that there is little probability of something happening. The group then went on to a discussion of how he should try to treat risk perception. One point that was made is that voluntary acceptance of a risk is important. A second point that was made on how to deal with risk perception problems is that the group could try to put the risk of radioactive waste disposal in the perspective of other risks to society, from the chemical industry for instance. The group also talked about the possibility of putting the benefits in perspective for people. Another point was that the group should have different communications strategies for different audiences. But, the more the public is involved in the decision making process, the more comfortable they are going to be with the risk, and the more consistent the perception of risk may be with the scientific definition thereof. In terms of new technologies, new innovations on the generation and management of waste, although these may actually

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

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

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

    International Nuclear Information System (INIS)

    2000-02-01

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

  18. 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

  19. 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...

  20. 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...

  1. Budget Options

    National Research Council Canada - National Science Library

    2000-01-01

    This volume-part of the Congressional Budget Office's (CBO's) annual report to the House and Senate Committees on the Budget-is intended to help inform policymakers about options for the federal budget...

  2. 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)

  3. 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

  4. 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

  5. The Electrical Engineering Curriculum at the Technical University of Denmark - Options in Microelectronics

    DEFF Research Database (Denmark)

    Bruun, Erik; Nielsen, Lars Drud

    1997-01-01

    This paper describes the modular structure of the engineering curriculum at the Technical University of Denmark. The basic requirements for an electrical engineering curriculum are presented and different possibilities for specialization in microelectronics and integrated circuit design...

  6. 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

  7. 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.

  8. 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.

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

    International Nuclear Information System (INIS)

    2002-03-01

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

  10. 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.

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

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

  13. 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...

  14. 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...

  15. Municipal waste processing: Technical/economic comparison of composting and incineration options

    International Nuclear Information System (INIS)

    Bertanza, G.

    1993-01-01

    The first part of this paper which assessed the state-of-the-art of municipal waste composting and incineration technologies indicated that the advanced level of available technologies in this field now allows the realization of reliable and safe plants. This second part of the paper deals with the economics of the composting and incineration options. Cost benefit analyses using the discounted cash flow method are made for waste processing plants featuring composting alone, incineration only and mixed composting and incineration. The economic analyses show that plants employing conventional composting techniques work well for the case of exclusively organic waste materials. Incineration schemes are shown to be economically effective when they incorporate suitable energy recovery systems. The integrated composting-incineration waste processing plant appears to be the least attractive option in terms of economics. Current R ampersand D activities in this field are being directed towards the development of systems with lower environmental impacts and capital and operating costs

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  17. 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

  18. 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.

  19. Technical backgrounder to CAPP input on June 14, 2002 workshop on federal climate change policy options

    International Nuclear Information System (INIS)

    2002-06-01

    This paper presents arguments regarding the Federal Discussion Paper on Climate Change which presents four options for Canada to implement the Kyoto Protocol. This paper describes some major flaws with the package. The Canadian Association of Petroleum Producers (CAPP) believes that policy on climate change should ensure that measures for the trade exposed industry sectors are based on achievable objectives and that all levels of government should take a coordinated approach to greenhouse gases. In addition there should be no unfair burden on any region or unfairness in any sector. Climate change policy objectives should also consider economic, environmental and social objectives. With respect to the Kyoto Protocol in particular, governments should assess the liability that ratification would create and determine whether it makes economic sense. CAPP argues that none of the four options in the federal discussion paper meets requirements for industry objectives and form of policies. In addition, if Canada does not shift industry and emissions to other countries, or buy foreign credits, energy use by consumers would have to be significantly reduced in order to meet the Kyoto target. It was also noted that if the 'polluter pay' policy proposal is to be adopted, it must be based on a thorough understanding of what it implies and be applied in such a way to reflect the reality of international markets

  20. Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

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

    DEFF Research Database (Denmark)

    Kovler, Konstantin; Jensen, Ole Mejlhede

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

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

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2001-07-31

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

  3. 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.

  4. 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

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

    International Nuclear Information System (INIS)

    1998-01-01

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

  6. 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. .

  7. 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.

  8. Glass melter materials technical options for the French vitrification process and operations experience authors

    International Nuclear Information System (INIS)

    Bonniaud, R.; Roznad, L.; Demay, R.

    1986-09-01

    The French vitrification process for solidifying high-level radioactive waste which has been under industrial application since 1978, is mentioned briefly. This technique involves glass melting at 1,150 deg.C, using an induction heated metallic vessel. The molten glass pouring is controlled by a thermal gate, which is also heated by induction. Two types of vessel are in use. Both are remotely removable and disposable to permit replacement at regular intervals. The technical criteria (the materials used have to meet) are described. The behaviour of the materials has been investigated using the industrial experience gained in the AVM facility during 8 years of operation, as well as with operation of a prototype for the new vitrification facilities under construction at La Hague. A short description of the use of these materials is also presented

  9. 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

  10. 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

  11. 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.

  12. 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

  13. Use of reprocessed uranium. Proceedings of a technical committee meeting held in Vienna, August 2007

    International Nuclear Information System (INIS)

    2009-11-01

    Reprocessed uranium (RepU), the uranium recovered from nuclear processing, is produced by several Member States in their facilities or through commercial contracts. From a sustainable development perspective, recycling of this uranium has become an attractive option for improving the efficiency of natural resource management and reducing radioactive waste accumulation. This publication demonstrates that reprocessing of spent fuel could form a key part of advanced fuel methodologies and describes various reuse options of RepU. In particular, it includes detailed review papers on management, storage, packaging and transport of RepU, reprocessing, utility experience and potential use of RepU. The importance of market aspects, economics and long term perspectives is also addressed

  14. Macro economic linkages and impacts. Technical and fiscal options in GHG abatement

    International Nuclear Information System (INIS)

    Backus, G.; Barker, T.

    1995-01-01

    This paper discusses some of the main macro economic linkages and feedbacks associated with policies for GHG abatement. The linkages in a global model are described when OECD carbon taxes or alternatively OECD/OPEC joint action raises world oil prices with a smaller OECD carbon tax. The results give a world perspective on the GHG abatement problem. The paper continues with a discussion of the linkages and feedbacks associated with three options: demand-side management (DSM), mainly to improve end-use energy efficiency, reductions in subsidies of fossil fuel production and use, and investment in renewable energy supplies, specifically in energy forestry and associated infrastructure. It concludes that DSM and investment in renewables are unlikely on their own to bring about reduction in GHG emissions, and that new supplies may even lead to increased emissions by driving down the price of energy. However, reductions in emissions may be compatible with increased efficiency and development, as well as with improvements in the quality of the local environment and in rural living, with the new supplies replacing fossil fuel supplies, provided that real fossil fuel prices are increased via removal of subsidies and if required carbon taxes. (au) 15 refs

  15. 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.

  16. 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

  17. 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.

  18. 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.

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. 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

  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. 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

  6. 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

  7. 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.

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

    International Nuclear Information System (INIS)

    2005-01-01

    activities as well as its participation in secondary supply sources such as commercialization of weapons grade uranium. Uranium supply from the developing countries could be increasingly important in satisfying worldwide reactor requirements over time. At the same time, it represents only one segment of total supply, which also includes production from developed countries plus secondary supply including inventory draw down, HEU, MOX, reprocessed uranium and re-enrichment of tails. A model developed by the IAEA is presented that provides for long term forecasting of uranium requirements for given sets of parameters including nuclear power projections and fuel cycle strategies. A companion presentation reviews the relationship between options at the backend of the nuclear fuel cycle and uranium market prices. These relationships impact the economics and therefore the availability of secondary supply

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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...

  16. 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

  17. 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.

  18. 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

  19. 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.

  20. 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

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

    International Nuclear Information System (INIS)

    1999-12-01

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

  2. 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.

  3. 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

  4. 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)

  5. 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).

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

    International Nuclear Information System (INIS)

    Humbert, D.; Wickham, A.J.

    2006-05-01

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

  7. 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.

  8. 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

  9. 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

  10. 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

  11. Scientific Opinion on a technical file submitted by the US Authorities to support a request to list a new option among the EU import requirements for wood of Agrilus planipennis host plants

    DEFF Research Database (Denmark)

    Baker, R.; Candresse, T.; Dormannsné Simon, E.

    2011-01-01

    This document presents the scientific opinion of the Panel on Plant Health on the technical file submitted by the US Authorities to support a request to list a new option among the EU import requirements for wood of Agrilus planipennis host plants. The option under consideration is a heat treatme...

  12. Policy implications of Iran's Nuclear Deal in technical terms for the plutonium route, uranium route, covert options, inspections, monitoring and verifications

    Energy Technology Data Exchange (ETDEWEB)

    Pinheiro, Andre Ricardo M., E-mail: andrericardopinheiro@usp.br [Universidade de São Paulo (USP), SP (Brazil). Departamento de Engenharia Naval; Guimarães, Leonam dos Santos, E-mail: leonam@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The present Paper addresses the policy implications of Joint Comprehensive Plan of Action (JCPOA) known as 'Ian Nuclear Deal', implemented on 16{sup th} January of 2016 between the Iran and the P5+1 countries (the U.S., U.K. France, Germany, Russia, and China), along with the EU in technical terms to analyze the Plutonium Route, Uranium Route and the Covert options and Inspections, Monitoring and Verifications. A historical review is presented to understand how the Iranian Nuclear Program is formed. Following is shown the current nuclear facilities in Iran and its capacity to process nuclear materials. It is analyzed the impact of JCPOA in Uranium and Plutonium routes. Covert Options always will be an option, so the most sensitive impact is related to the new monitoring and verification policies that must ensure real control of illegal procedures. The main conclusion is that the deal postpones the Iran's nuclear program for more than a decade (15 years), delaying Iran's nuclear bomb time from a few months to at least one year, although there is a current latent capacity to develop a nuclear bomb in Uranium route. It also gives IAEA inspectors capability to monitor nuclear activities and prevent to possible development to a nuclear bomb. To arrive in this conclusion an extensive technical analyze of impact of JCPOA in Iran's nuclear capabilities was made to discover how effective is the deal to prevent Iran to build, or acquire a nuclear weapon. (author)

  13. Policy implications of Iran's Nuclear Deal in technical terms for the plutonium route, uranium route, covert options, inspections, monitoring and verifications

    International Nuclear Information System (INIS)

    Pinheiro, Andre Ricardo M.

    2017-01-01

    The present Paper addresses the policy implications of Joint Comprehensive Plan of Action (JCPOA) known as 'Ian Nuclear Deal', implemented on 16 th January of 2016 between the Iran and the P5+1 countries (the U.S., U.K. France, Germany, Russia, and China), along with the EU in technical terms to analyze the Plutonium Route, Uranium Route and the Covert options and Inspections, Monitoring and Verifications. A historical review is presented to understand how the Iranian Nuclear Program is formed. Following is shown the current nuclear facilities in Iran and its capacity to process nuclear materials. It is analyzed the impact of JCPOA in Uranium and Plutonium routes. Covert Options always will be an option, so the most sensitive impact is related to the new monitoring and verification policies that must ensure real control of illegal procedures. The main conclusion is that the deal postpones the Iran's nuclear program for more than a decade (15 years), delaying Iran's nuclear bomb time from a few months to at least one year, although there is a current latent capacity to develop a nuclear bomb in Uranium route. It also gives IAEA inspectors capability to monitor nuclear activities and prevent to possible development to a nuclear bomb. To arrive in this conclusion an extensive technical analyze of impact of JCPOA in Iran's nuclear capabilities was made to discover how effective is the deal to prevent Iran to build, or acquire a nuclear weapon. (author)

  14. 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

  15. 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

  16. 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

  17. Main technical options of the Jules Horowitz reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 kW/I for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: - A safety approach based upon the defence-in-depth principle. - A strategy of generic approaches to assess experimental risks in the facility. - Internal events analysis taking into account risks linked to reactor and experiments (e.g., radioactive source-term). - Systematic consideration of external hazards (e.g., earthquake, airplane crash) and internal hazards. - Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (authors)

  18. Main technical options of the Jules Horowitz Reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 KW/l for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: 1) A safety approach based upon the defence-in-depth principle. 2) A strategy of generic approaches to assess experimental risks in the facility. 3) Internal events analysis taking into account risks linked to reactor and experiments (eg., radioactive source-term). 4) Systematic consideration of external hazards (eg., earthquake, airplane crash) and internal hazards. 5) Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (author)

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. Solar heating and cooling of buildings (SHACOB) commercialization report: options and strategies. Part A. Volume II. Technical report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1977-07-15

    The national and regional perspectives for SHACOB are presented. An overview is given of the participants in SHACOB commercialization. Economic, institutional, legal, and other barriers constraining commercialization are discussed. Various analytical models are examined which project the future extent of SHACOB use or market penetration and future SHACOB to US energy supplies under alternative government policies. The results for the baseline case (no further government action, of several market penetration models are presented. Possible ways to overcome each of the barriers are presented. Qualitative analyses are given for the various incentives. Each incentive is examined to assess its impact on barriers to SHACOB commercialization and its impact on various income and interest groups. Individual incentives are compared and combined into alternative policy strategies and options. (MHR)

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

    International Nuclear Information System (INIS)

    1997-09-01

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

  7. Intra-extramedullary drainage as an effective option for treatment of intramedullary ependymal cyst of thoracic spine: technical note.

    Science.gov (United States)

    Landi, Alessandro; Pietrantonio, Andrea; Marotta, Nicola; Mancarella, Cristina; Delfini, Roberto

    2014-03-01

    Intramedullary neuroepithelial cysts are extremely rare and only 15 cases have been reported in the literature. Clinico-radiological features are not indicative of a specific diagnosis; for this reason, diagnosis is based mainly on the histological features. In the literature, total surgical removal is considered the treatment of choice. The risk of recurrence is higher after partial removal and in cases of occlusion of intra-extramedullary shunt. For this reason, a surgical strategy that ensures the shunt patency in case of incomplete removal of the cyst becomes a very safe option for treatment of this pathology. We report the case of a 51-year-old woman who was found to have a dorsal (D9) intramedullary neuroepithelial cyst. She underwent surgical treatment with partial removal and placement of a Nelaton drainage device (8 French) inside the intra-extramedullary shunt. The patient experienced a complete regression of preoperative symptoms and magnetic resonance imaging (MRI) follow-up showed no radiological evidence of recurrence 24 months after surgical treatment. Spinal ependymal cysts show a high frequency of recurrence, especially in cases of partial removal of the cyst wall. Unfortunately, the cyst walls are often closely adherent to the spinal cord, making total removal impossible. Intra-extramedullary shunting is a viable option, although there is a high frequency of recurrence in cases of obstruction of the shunt. Placing an 8 Ch Nelaton drain between the dorsal columns is a reliable technique, especially in cases of partial removal. In fact, it allows continuous drainage of cyst fluid and subsequent resolution of symptoms, and it decreases the incidence of recurrences due to obstruction of the shunt. Georg Thieme Verlag KG Stuttgart · New York.

  8. 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

  9. A combined model to assess technical and economic consequences of changing conditions and management options for wastewater utilities.

    Science.gov (United States)

    Giessler, Mathias; Tränckner, Jens

    2018-02-01

    The paper presents a simplified model that quantifies economic and technical consequences of changing conditions in wastewater systems on utility level. It has been developed based on data from stakeholders and ministries, collected by a survey that determined resulting effects and adapted measures. The model comprises all substantial cost relevant assets and activities of a typical German wastewater utility. It consists of three modules: i) Sewer for describing the state development of sewer systems, ii) WWTP for process parameter consideration of waste water treatment plants (WWTP) and iii) Cost Accounting for calculation of expenses in the cost categories and resulting charges. Validity and accuracy of this model was verified by using historical data from an exemplary wastewater utility. Calculated process as well as economic parameters shows a high accuracy compared to measured parameters and given expenses. Thus, the model is proposed to support strategic, process oriented decision making on utility level. Copyright © 2017 Elsevier Ltd. All rights reserved.

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. 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...

  16. 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

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

    International Nuclear Information System (INIS)

    2000-05-01

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

  18. 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.

  19. 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.

  20. 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.

  1. 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

  2. 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.

  3. 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

  4. 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.

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

    International Nuclear Information System (INIS)

    2002-01-01

    invited to fulfil the attached Technical Background Form

  6. 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...

  7. Energy options

    International Nuclear Information System (INIS)

    Hampton, Michael

    1999-01-01

    This chapter focuses on energy options as a means of managing exposure to energy prices. An intuitive approach to energy options is presented, and traditional definitions of call and put options are given. The relationship between options and swaps, option value and option exercises, commodity options, and option pricing are described. An end-user's guide to energy option strategy is outlined, and straight options, collars, participating swaps and collars, bull and bear spreads, and swaption are examined. Panels explaining the defining of basis risk, and discussing option pricing and the Greeks, delta hedging, managing oil options using the Black-Scholes model, caps, floors and collars, and guidelines on hedging versus speculation with options are included in the paper

  8. 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...

  9. 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...

  10. 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...

  11. Advisory Committee on the Redesign of the Space Station

    Science.gov (United States)

    1993-06-01

    The Space Station Program was initiated in 1984 to provide for permanent human presence in an orbiting laboratory. This program evolved into Space Station Freedom, later identified as a component to facilitate a return of astronauts to the Moon, followed by the exploration of Mars. In March 1993 the Clinton Administration directed NASA to undertake an intense effort to redesign the space station at a substantial cost savings relative to Space Station Freedom. The Advisory Committee on the Redesign of the Space Station was established in March 1993 to provide independent assessment of the advantages and disadvantages of the redesign options. The results of the Committee's work is described. Discussion describes the mission that the Administration has articulated for the Space Station Program and the scientific and technical characteristics that a redesigned station must possess to fulfill those objectives. A description of recommended management, operations, and acquisition strategies for the redesigned program is provided. The Committee's assessment of the redesign options against five criteria are presented. The five criteria are technical capabilities, research capabilities, schedule, cost, and risk. A discussion of general mission risk is included.

  12. Recidiva pós cardiomiotomia: diagnóstico, opções técnicas e resultados Recurrence after cardiomyotomy: diagnosis, technical options and results

    Directory of Open Access Journals (Sweden)

    Hélio Ponciano Trevenzol

    2010-03-01

    -recurrence. RESULTS: Surgical options for treatment of relapsed megaesophagus are shown in forms so varied and personal with technical details and diverse. The techniques recommended were basically: remyotomy, cardioplasty, esophagectomy and mucosectomy, including variants of these operations. CONCLUSION: The choice of technique should be individualized based on the cause of relapse, which should be thoroughly investigated preoperatively. The remyotomy represents the most feasible alternative, with lower morbidity and satisfactory results and effectiveness in the improvement of dysphagia, but with mild esophagitis in 40% and lower level of satisfaction over the years after surgery, reaching 57,1% after 20 years.

  13. 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.)

  14. 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...

  15. 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

  16. 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.

  17. 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.

  18. Trends in Connectivity Technologies and Their Socioeconomic Impacts. Final Report of the Study: Policy Options for the Ubiquitous Internet Society. Technical Report

    Science.gov (United States)

    Cave, Jonathan; van Oranje-Nassau, Constantijn; Schindler, Helen Rebecca; Shehabi, Ala'a; Brutscher, Philipp-Bastian; Robinson, Neil

    2009-01-01

    This report is intended to inform the European Commission's DG Information Society and Media in developing its policies for the period 2010-2020. It is targeted to policymakers with expert knowledge of the field. The report summarises the work conducted in the study: "Policy Options for the Ubiquitous Internet Society". It builds on…

  19. 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*.

  20. Rehabilitation Options

    Science.gov (United States)

    ... Speech Pathology Occupational Therapy Art Therapy Recreational therapy Neuropsychology Home Care Options Advanced Care Planning Palliative Care ... Speech Pathology Occupational Therapy Art Therapy Recreational therapy Neuropsychology Home Care Options Advanced Care Planning Palliative Care ...

  1. 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...

  2. Strategies for the back end of the nuclear fuel cycle. Proceedings of a technical committee meeting held in Vienna, 1-4 June 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The selection of an option for the back end of the nuclear fuel cycle is an important decision for all countries with nuclear power programmes. Likewise, the process for making that option selection is also important. Some countries have begun utilizing nuclear energy for electricity generation without formally determining what would be done with the spent nuclear fuel and radioactive wastes. In a number of those countries the inventories of spent fuel are approaching their storage capacity - and an option selection must soon be made. This report provides an analysis of both the policies chosen by a number of Member States and the process that led to those selections. The intent of this analysis and this publication is to assist other countries in their deliberations on this subject. This publication presents conclusions concerning the factors that were considered important by different countries and the processes which they followed in making their determination of the policy for disposal of nuclear waste. Refs, figs, tabs.

  3. Strategies for the back end of the nuclear fuel cycle. Proceedings of a technical committee meeting held in Vienna, 1-4 June 1993

    International Nuclear Information System (INIS)

    1995-11-01

    The selection of an option for the back end of the nuclear fuel cycle is an important decision for all countries with nuclear power programmes. Likewise, the process for making that option selection is also important. Some countries have begun utilizing nuclear energy for electricity generation without formally determining what would be done with the spent nuclear fuel and radioactive wastes. In a number of those countries the inventories of spent fuel are approaching their storage capacity - and an option selection must soon be made. This report provides an analysis of both the policies chosen by a number of Member States and the process that led to those selections. The intent of this analysis and this publication is to assist other countries in their deliberations on this subject. This publication presents conclusions concerning the factors that were considered important by different countries and the processes which they followed in making their determination of the policy for disposal of nuclear waste. Refs, figs, tabs

  4. 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...

  5. 77 FR 35944 - Renewal of the Global Markets Advisory Committee

    Science.gov (United States)

    2012-06-15

    ... international standards for regulating futures, swaps, options, and derivatives markets, as well as..., competitive, and financially sound futures and options markets. Meetings of the Global Markets Advisory... COMMODITY FUTURES TRADING COMMISSION Renewal of the Global Markets Advisory Committee AGENCY...

  6. Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

    Energy Technology Data Exchange (ETDEWEB)

    Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

    1993-06-01

    The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

  7. Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

    International Nuclear Information System (INIS)

    Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

    1993-06-01

    The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition

  8. Alternative energy options

    International Nuclear Information System (INIS)

    Bennett, K.F.

    1983-01-01

    It is accepted that coal will continue to play the major role in the supply of energy to the country for the remainder of the century. In this paper, however, emphasis has been directed to those options which could supplement coal in an economic and technically sound manner. The general conclusion is that certain forms of solar energy hold the most promise and it is in this direction that research, development and implementation programmes should be directed. Tidal energy, fusion energy, geothermal energy, hydrogen energy and fuel cells are also discussed as alternative energy options

  9. 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.

  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. 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

  12. 78 FR 27963 - Reliability Technical Conference; Notice of Technical Conference

    Science.gov (United States)

    2013-05-13

    ... Technical Conference; Notice of Technical Conference Take notice that the Federal Energy Regulatory Commission will hold a Technical Conference on Tuesday, July 9, 2013 from 9:00 a.m. to 5:00 p.m. This... technical support for webcasts and offers the option of listening to the meeting via phone-bridge for a fee...

  13. 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...

  14. 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 ...

  15. Options for Tsetse Eradication in the Moist Savannah Zone of West Africa: Technical and Economic Feasibility, Phase 1 - GIS-Based Study. Programme Against African Trypanosomiasis

    International Nuclear Information System (INIS)

    2001-12-01

    This desk study was initiated with two objectives: - To examine the economic costs and benefits of a range of different sized tsetse eradication projects in the Moist Savannah Zone of West Africa (MSZ), and; - To test the hypothesis that larger tsetse control projects are more economically efficient than smaller projects in that region. The limited nature of the study precluded detailed examination of the socio-cultural and environmental issues relating to controlling trypanosomosis although these are briefly considered; nor did it aim to compare vector control with other methods of combating trypanosomosis such as the therapeutic or prophylactic use of drugs. However, by computing benefits over just 10 years an indirect comparison is made with the strategy that maintains that eradicating tsetse flies is not justified as, sooner or later, rapidly increasing population pressure will autonomously eradicate tsetse flies and hence trypanosomosis. This analysis suggests that such a strategy is not justified economically. As the basis of the economic evaluation was a study of projects in defined areas it was first necessary to iteratively examine the technical and economic issues relating to project selection and design. In this respect, the re-invasion issue was considered to be the major influence as it threatens both the sustainability and economic performance of tsetse eradication. Consequently, it was considered that the river basin was the smallest size of project that would optimise economic performance. This particular observation relates uniquely to the MSZ and may not apply to more southerly areas where fly distribution is more ubiquitous or to other parts of Africa. By basing the economic analysis on an evaluation of projects, albeit hypothetical, it was possible to use real data as the baseline database and the projects could be designed in response to actual tsetse and trypanosomosis scenarios. The group of study areas were chosen to be representative of the

  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. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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

  2. 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

  3. Nevada Transportation Options Study

    International Nuclear Information System (INIS)

    P. GEHNER; E.M. WEAVER; L. FOSSUM

    2006-01-01

    This study performs a cost and schedule analysis of three Nevada Transportation options that support waste receipt at the repository. Based on the U.S. Department of Energy preference for rail transportation in Nevada (given in the Final Environmental Impact Statement), it has been assumed that a branch rail line would be constructed to support waste receipt at the repository. However, due to potential funding constraints, it is uncertain when rail will be available. The three Nevada Transportation options have been developed to meet a varying degree of requirements for transportation and to provide cost variations used in meeting the funding constraints given in the Technical Direction Letter guidelines for this study. The options include combinations of legal-weight truck, heavy-haul truck, and rail. Option 1 uses a branch rail line that would support initial waste receipt at the repository in 2010. Rail transportation would be the primary mode, supplemented by legal weight trucks. This option provides the highest level of confidence in cost and schedule, lowest public visibility, greatest public acceptability, lowest public dose, and is the recommended option for support of waste receipt. The completion of rail by 2010 will require spending approximately $800 million prior to 2010. Option 2 uses a phased rail approach to address a constrained funding scenario. To meet funding constraints, Option 2 uses a phased approach to delay high cost activities (final design and construction) until after initial waste receipt in 2010. By doing this, approximately 95 percent of the cost associated with completion of a branch rail line is deferred until after 2010. To support waste receipt until a branch rail line is constructed in Nevada, additional legal-weight truck shipments and heavy-haul truck shipments (on a limited basis for naval spent nuclear fuel) would be used to meet the same initial waste receipt rates as in Option 1. Use of heavy-haul shipments in the absence

  4. Options Study - Phase II

    Energy Technology Data Exchange (ETDEWEB)

    R. Wigeland; T. Taiwo; M. Todosow; W. Halsey; J. Gehin

    2010-09-01

    The Options Study has been conducted for the purpose of evaluating the potential of alternative integrated nuclear fuel cycle options to favorably address the issues associated with a continuing or expanding use of nuclear power in the United States. The study produced information that can be used to inform decisions identifying potential directions for research and development on such fuel cycle options. An integrated nuclear fuel cycle option is defined in this study as including all aspects of the entire nuclear fuel cycle, from obtaining natural resources for fuel to the ultimate disposal of used nuclear fuel (UNF) or radioactive wastes. Issues such as nuclear waste management, especially the increasing inventory of used nuclear fuel, the current uncertainty about used fuel disposal, and the risk of nuclear weapons proliferation have contributed to the reluctance to expand the use of nuclear power, even though it is recognized that nuclear power is a safe and reliable method of producing electricity. In this Options Study, current, evolutionary, and revolutionary nuclear energy options were all considered, including the use of uranium and thorium, and both once-through and recycle approaches. Available information has been collected and reviewed in order to evaluate the ability of an option to clearly address the challenges associated with the current implementation and potential expansion of commercial nuclear power in the United States. This Options Study is a comprehensive consideration and review of fuel cycle and technology options, including those for disposal, and is not constrained by any limitations that may be imposed by economics, technical maturity, past policy, or speculated future conditions. This Phase II report is intended to be used in conjunction with the Phase I report, and much information in that report is not repeated here, although some information has been updated to reflect recent developments. The focus in this Options Study was to

  5. Retrieval options study

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    This Retrieval Options Study is part of the systems analysis activities of the Office of Nuclear Waste Isolation to develop the scientific and technological bases for radioactive waste repositories in various geologic media. The study considers two waste forms, high level waste and spent fuel, and defines various classes of waste retrieval and recovery. A methodology and data base are developed which allow the relative evaluation of retrieval and recovery costs and the following technical criteria: safety; technical feasibility; ease of retrieval; probable intact retrieval time; safeguards; monitoring; criticality; and licensability. A total of 505 repository options are defined and the cost and technical criteria evaluated utilizing a combination of facts and engineering judgments. The repositories evaluated are selected combinations of the following parameters: Geologic Media (salt, granite, basalt, shale); Retrieval Time after Emplacement (5 and 25 years); Emplacement Design (nominal hole, large hole, carbon steel canister, corrosion resistant canister, backfill in hole, nominal sleeves, thick wall sleeves); Emplacement Configuration (single vertical, multiple vertical, single horizontal, multiple horizontal, vaults; Thermal Considerations; (normal design, reduced density, once-through ventilation, recirculated ventilation); Room Backfill; (none, run-of-mine, early, 5 year delay, 25 year delay, decommissioned); and Rate of Retrieval; (same as emplacement, variably slower depending on repository/canister condition).

  6. Retrieval options study

    International Nuclear Information System (INIS)

    1980-03-01

    This Retrieval Options Study is part of the systems analysis activities of the Office of Nuclear Waste Isolation to develop the scientific and technological bases for radioactive waste repositories in various geologic media. The study considers two waste forms, high level waste and spent fuel, and defines various classes of waste retrieval and recovery. A methodology and data base are developed which allow the relative evaluation of retrieval and recovery costs and the following technical criteria: safety; technical feasibility; ease of retrieval; probable intact retrieval time; safeguards; monitoring; criticality; and licensability. A total of 505 repository options are defined and the cost and technical criteria evaluated utilizing a combination of facts and engineering judgments. The repositories evaluated are selected combinations of the following parameters: Geologic Media (salt, granite, basalt, shale); Retrieval Time after Emplacement (5 and 25 years); Emplacement Design (nominal hole, large hole, carbon steel canister, corrosion resistant canister, backfill in hole, nominal sleeves, thick wall sleeves); Emplacement Configuration (single vertical, multiple vertical, single horizontal, multiple horizontal, vaults; Thermal Considerations; (normal design, reduced density, once-through ventilation, recirculated ventilation); Room Backfill; (none, run-of-mine, early, 5 year delay, 25 year delay, decommissioned); and Rate of Retrieval;

  7. Mixed waste management options

    International Nuclear Information System (INIS)

    Owens, C.B.; Kirner, N.P.

    1992-01-01

    Currently, limited storage and treatment capacity exists for commercial mixed waste streams. No commercial mixed waste disposal is available, and it has been estimated that if and when commercial mixed waste disposal becomes available, the costs will be high. If high disposal fees are imposed, generators may be willing to apply extraordinary treatment or regulatory approaches to properly dispose of their mixed waste. This paper explores the feasibility of several waste management scenarios and management options. Existing data on commercially generated mixed waste streams are used to identify the realm of mixed waste known to be generated. Each waste stream is evaluated from both a regulatory and technical perspective in order to convert the waste into a strictly low-level radioactive or a hazardous waste. Alternative regulatory approaches evaluated in this paper include a delisting petition) no migration petition) and a treatability variance. For each waste stream, potentially available treatment options are identified that could lead to these variances. Waste minimization methodology and storage for decay are also considered. Economic feasibility of each option is discussed broadly. Another option for mixed waste management that is being explored is the feasibility of Department of Energy (DOE) accepting commercial mixed waste for treatment, storage, and disposal. A study has been completed that analyzes DOE treatment capacity in comparison with commercial mixed waste streams. (author)

  8. Energy options?; Energie opties?

    Energy Technology Data Exchange (ETDEWEB)

    Van Sark, W. (ed.)

    2006-05-15

    March 2006 the so-called Options Document was published by the Energy research Centre of the Netherlands (ECN) and the Netherlands Environmental Assessment Agency (MNP). The document is an overview of technical options to reduce energy consumption and emission of greenhouse gases up to 2020. Next to a brief summary of the document a few reactions and comments on the contents of the document are given. [Dutch] Maart 2006 publiceerde het Energieonderzoek Centrum Nederland (ECN) en het Milieu- en Natuurplanbureau (MNP) het zogenaamde Optiedocument energie en emissies 2010-2020. Daarin wordt een overzicht gegeven van de technische mogelijkheden voor vermindering van het energieverbruik en de uitstoot van broeikasgassen en luchtverontreinigende stoffen tot 2020. Naast een korte samenvatting van het document worden enkele reacties gegeven op de inhoud.

  9. Evaluating technology service options.

    Science.gov (United States)

    Blumberg, D F

    1997-05-01

    Four service and support options are available to healthcare organizations for maintaining their growth arsenals of medical and information technology. These options include maintaining and servicing all equipment using a facility-based biomedical engineering and MIS service department; using a combination of facility-based service and subcontracted service; expanding facility-based biomedical and MIS service departments to provide service to other healthcare organizations to achieve economies of scale; and outsourcing all maintenance, repair, and technical support services. Independent service companies and original equipment manufacturers (OEMs) are offering healthcare organizations a wider array of service and support capabilities than ever before. However, some health systems have successfully developed their own independent service organizations to take care of their own--and other healthcare organizations'--service and support needs.

  10. 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

  11. Energy exotic options

    International Nuclear Information System (INIS)

    Kaminski, V.; Gibner, S.; Pinnamaneni, K.

    1999-01-01

    This chapter with 88 references focuses on the use of exotic options to control exposure to energy prices. Exotic options are defined, and the conversion of a standard option into an exotic option and pricing models are examined. Pricing and hedging exotic options, path-dependent options, multi-commodity options, options on the minimum-or-maximum of two commodities, compound options, digital options, hybrid and complex structures, and natural gas daily options are described. Formulas for option pricing for vanilla, barrier, compound, options on minimum or maximum of two assets, and look back options are given in an appendix

  12. 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...

  13. 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...

  14. 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.

  15. Options theory

    International Nuclear Information System (INIS)

    Markland, J.T.

    1992-01-01

    Techniques used in conventional project appraisal are mathematically very simple in comparison to those used in reservoir modelling, and in the geosciences. Clearly it would be possible to value assets in mathematically more sophisticated ways if it were meaningful and worthwhile so to do. The DCf approach in common use has recognized limitations; the inability to select a meaningful discount rate being particularly significant. Financial Theory has advanced enormously over the last few years, along with computational techniques, and methods are beginning to appear which may change the way we do project evaluations in practice. The starting point for all of this was a paper by Black and Scholes, which asserts that almost all corporate liabilities can be viewed as options of varying degrees of complexity. Although the financial presentation may be unfamiliar to engineers and geoscientists, some of the concepts used will not be. This paper outlines, in plain English, the basis of option pricing theory for assessing the market value of a project. it also attempts to assess the future role of this type of approach in practical Petroleum Exploration and Engineering economics. Reference is made to relevant published Natural Resource literature

  16. The UK Committee on Radioactive Waste Management

    International Nuclear Information System (INIS)

    Baverstock, Keith; Ball, David J

    2005-01-01

    The UK Committee on Radioactive Waste Management is charged with recommending to Government, by July 2006, options for the long term management of the UK's radioactive waste legacy. These options should inspire public confidence. Now, more than halfway into the time allotted, we, as two former members of the Committee, express our concerns at the wayward approach that has been adopted. The Committee has placed emphasis on gaining public confidence but this has been done at the expense of recruiting the best scientific expertise in the management of radioactive waste, an act which we believe will actually undermine public confidence. Furthermore, given also the immense importance of this decision to public safety, national security and the national interest, we believe urgent steps should be taken to review the Committee's process, its management and its sponsorship. (opinion)

  17. Shungnak Energy Configuration Options.

    Energy Technology Data Exchange (ETDEWEB)

    Rosewater, David Martin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Eddy, John P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-10-01

    Power systems in rural Alaska villages face a unique combination of challenges that can increase the cost of energy and lowers energy supply reliability. In the case of the remote village of Shungnak, diesel and heating fuel is either shipped in by barge or flown in by aircraft. This report presents a technical analysis of several energy infrastructure upgrade and modification options to reduce the amount of fuel consumed by the community of Shungnak. Reducing fuel usage saves money and makes the village more resilient to disruptions in fuel supply. The analysis considers demand side options, such as energy efficiency, alongside the installation of wind and solar power generation options. Some novel approaches are also considered including battery energy storage and the use of electrical home heating stoves powered by renewable generation that would otherwise be spilled and wasted. This report concludes with specific recommendations for Shungnak based on economic factors, and fuel price sensitivity. General conclusions are also included to support future work analyzing similar energy challenges in remote arctic regions.

  18. The safeguards options study

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D. [Los Alamos National Lab., NM (United States); Olsen, A.P.; Roche, C.T.; Rudolph, R.R. [Argonne National Lab., IL (United States); Bieber, A.M.; Lemley, J. [Brookhaven National Lab., Upton, NY (United States); Filby, E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

    1995-04-01

    The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq`s obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state.

  19. The safeguards options study

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D.; Olsen, A.P.; Roche, C.T.; Rudolph, R.R.; Bieber, A.M.; Lemley, J.; Filby, E.

    1995-04-01

    The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq's obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state

  20. New Commitment Options: Compatibility with Emissions Trading

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This paper considers different options for quantitative greenhouse gas emission commitments from the standpoint of their technical compatibility with emissions trading. These are dynamic targets, binding targets with price caps, non-binding targets, sector-wide targets/mechanisms, action targets, allowances and endowments, and long-term permits. This paper considers these options from the standpoint of their compatibility with emissions trading.

  1. Buridan's Ass and a Menu of Options.

    OpenAIRE

    Svetlana Boyarchenko

    2005-01-01

    The goal of the paper is to study how a menu of options affects decisions of a rational agent facing uncertainty over future payoff streams. Using the real options approach, we demonstrate that multiple options not only increase the barrier which the underlying stochastic variable has to reach in order investment became optimal, but cause the investor to be inactive even when the cost of investment is vanishing. As a technical contribution, the paper suggests a robust method of solution of a ...

  2. 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....

  3. 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

  4. 75 FR 33788 - Renewal of the Global Markets Advisory Committee

    Science.gov (United States)

    2010-06-15

    ... appropriate international standards for regulating futures and derivatives markets, as well as intermediaries... financially sound futures and options markets. Meetings of the Global Markets Advisory Committee are open to... COMMODITY FUTURES TRADING COMMISSION Renewal of the Global Markets Advisory Committee AGENCY...

  5. A nuclear fuel cycle system dynamic model for spent fuel storage options

    International Nuclear Information System (INIS)

    Brinton, Samuel; Kazimi, Mujid

    2013-01-01

    Highlights: • Used nuclear fuel management requires a dynamic system analysis study due to its socio-technical complexity. • Economic comparison of local, regional, and national storage options is limited due to the public financial information. • Local and regional options of used nuclear fuel management are found to be the most economic means of storage. - Abstract: The options for used nuclear fuel storage location and affected parameters such as economic liabilities are currently a focus of several high level studies. A variety of nuclear fuel cycle system analysis models are available for such a task. The application of nuclear fuel cycle system dynamics models for waste management options is important to life-cycle impact assessment. The recommendations of the Blue Ribbon Committee on America’s Nuclear Future led to increased focus on long periods of spent fuel storage [1]. This motivated further investigation of the location dependency of used nuclear fuel in the parameters of economics, environmental impact, and proliferation risk. Through a review of available literature and interactions with each of the programs available, comparisons of post-reactor fuel storage and handling options will be evaluated based on the aforementioned parameters and a consensus of preferred system metrics and boundary conditions will be provided. Specifically, three options of local, regional, and national storage were studied. The preliminary product of this research is the creation of a system dynamics tool known as the Waste Management Module (WMM) which provides an easy to use interface for education on fuel cycle waste management economic impacts. Initial results of baseline cases point to positive benefits of regional storage locations with local regional storage options continuing to offer the lowest cost

  6. Low activity resin processing and disposal options review

    International Nuclear Information System (INIS)

    Gardner, F.

    1996-01-01

    New processing options for low activity resin processing and disposal are available. This presentation reviews the economics and technical requirements associated with the following low activity resin processing options. (1) Bulk release resin. (2) Direct disposal. (3) Decontamination and bulk release of cleaned resin. New processing and disposal options have been developed during 1995. Commercial experience with each of these options will be reviewed and the economics associated with the processing method described in detail. Technical requirements for each option will be identified specifying the activity limits and operational requirements for implementation

  7. Treatment Options for Retinoblastoma

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other places in the body. Treatment Option Overview Key Points There are different types of ...

  8. 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.)

  9. 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)

  10. Safety options for the 1300 MWe program

    International Nuclear Information System (INIS)

    Cayol, A.; Dupuis, M.C.; Fourest, B.; Oury, J.M.

    1980-04-01

    Standardization of the nuclear plants built in France implies an examination of the main technical safety options to be taken for a given type of reactor. By this procedure the subjects for which detailed studies will be needed to confirm the decisions made for the project can be defined in advance. In this context the technical safety option analysis for the 1300 MWe plants was conducted from the end of 1975 to the middle of 1978 according to usual regulation examination practice. The main conclusions are presented on the following subjects: safety methods; technical options concerning the containment vessel, primary fluid activity, fuel elements, steam generators; general organization of the lay-out [fr

  11. Options for rural electrification in Mexico

    International Nuclear Information System (INIS)

    Vera, J.G.

    1992-01-01

    This paper summarizes a study which examined 19 commercially available options for electrifying remote communities in Mexico. Characteristics of a typical community are defined and, using 7 of the technologies, power systems are designed capable of supporting this community. The performance of these systems is evaluated with respect to their ability to satisfy 11 technical design objectives, 5 socioeconomic objectives, and their impact on the environment. A photovoltaic- diesel generator hybrid system with wind generator option is recommended for the typical community

  12. The Gel Generator option

    International Nuclear Information System (INIS)

    Boyd, R.E.

    1999-01-01

    The development of a national policy for guaranteeing an ample supply of 99m Tc to nuclear medicine, involves issues which go beyond the means by which radioactivation is achieved. Indeed, in such an exercise the pragmatic dictates of business and the sensitivities of politics must also be taken into account. Furthermore where a preference towards the nuclear reactor or the potential of cyclotrons is being questioned, the debate is incomplete if the only options that are considered are the fission-based 99 Mo generator versus the direct cyclotron production of 99m Tc. There is a third option (also neutron γ-based), an alternative to the fission 99 Mo generator, which ought not be overlooked. The application of low specific activity (n,γ) 99 Mo to a new type of generator, the Gel Generator, has been the focus of much research, particularly in Australia and more recently in China. After the initial concept had been established in the laboratory, the Australian researchers then undertook a comprehensive program of tests on the Gel Generator to assess its potential, either in the clinical laboratory or the centralised radiopharmacy, for supplying 99m Tc suitable for nuclear medicine. The outcome of this program was a clear indication that the Gel Generator innovation had the capability to provide both technical and economic advantages to the nuclear medicine industry. These advantages are described. Since that time the Gel Generator has been selected for routine use in China where it now satisfies more than 30% of the 99m Tc demand. (author)

  13. Australian Asian Options

    OpenAIRE

    Manuel Moreno; Javier F. Navas

    2003-01-01

    We study European options on the ratio of the stock price to its average and viceversa. Some of these options are traded in the Australian Stock Exchange since 1992, thus we call them Australian Asian options. For geometric averages, we obtain closed-form expressions for option prices. For arithmetic means, we use different approximations that produce very similar results.

  14. Options with Extreme Strikes

    Directory of Open Access Journals (Sweden)

    Lingjiong Zhu

    2015-07-01

    Full Text Available In this short paper, we study the asymptotics for the price of call options for very large strikes and put options for very small strikes. The stock price is assumed to follow the Black–Scholes models. We analyze European, Asian, American, Parisian and perpetual options and conclude that the tail asymptotics for these option types fall into four scenarios.

  15. Methodology for technical risk assessment

    International Nuclear Information System (INIS)

    Waganer, L.M.; Zuckerman, D.S.

    1983-01-01

    A methodology has been developed for and applied to the assessment of the technical risks associated with an evolving technology. This methodology, originally developed for fusion by K. W. Billman and F. R. Scott at EPRI, has been applied to assess the technical risk of a fuel system for a fusion reactor. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications (i.e. probability of failure). The individual steps in the technical risk assessment are summarized. The first step in this methodology is to clearly and completely quantify the technical requirements for the particular system being examined. The next step is to identify and define subsystems and various options which appear capable of achieving the required technical performance. The subsystem options are then characterized regarding subsystem functions, interface requirements with the subsystems and systems, important components, developmental obstacles and technical limitations. Key technical subsystem performance parameters are identified which directly or indirectly relate to the system technical specifications. Past, existing and future technical performance data from subsystem experts are obtained by using a Bayesian Interrogation technique. The input data is solicited in the form of probability functions. Thus the output performance of the system is expressed as probability functions

  16. NHTSA's Office of Defects Investigation (ODI) - Technical Service Bulletins System (TSBS) - Downloadable file

    Data.gov (United States)

    Department of Transportation — The Technical Service Bulletins data contains summaries of the Manufacturers' Technical Service Bulletins by single year, make and model. An optional item of Vehicle...

  17. The Audit Committee. AGB Effective Committee Series

    Science.gov (United States)

    Staisloff, Richard L.

    2011-01-01

    This publication is part of an Association of Governing Boards of Universities and Colleges (AGB) series devoted to strengthening the role of key standing committees of governing boards. While there is no optimum committee system for institutions of higher education, certain principles, practices, and procedures prevail. The best practices…

  18. The Investment Committee. Effective Committees. Board Basics.

    Science.gov (United States)

    Biggs, John H.

    1997-01-01

    The investment committee of the college or university governing board is charged with determining, overseeing, and assessing the policies and processes by which institutional funds are invested. The committee has fiduciary duty to ensure that the terms of investment of donors' gifts are met and to maximize investment returns within an appropriate…

  19. Report on the second meeting of the project advisory committee (technical) for IAEA/WHO project EGY/6/004 (Egyptian Cancer Project) 3-9 April 1984, at NEMROCK, Cairo

    International Nuclear Information System (INIS)

    Taylor, C.G.B.

    1984-07-01

    The purpose of the meeting was to review the first year's work and make recommendations for the future. The Committee dealt mainly with the Training Course, the selection of cases suitable for treatment by simple means, the revision of treatment notes and protocols, planning for the cytology (early diagnosis) programme, the collection and manipulation of data, the extension of the Project in Egypt, and its possible extension to other countries

  20. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    International Nuclear Information System (INIS)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations

  1. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

  2. Advisory Committee Handbook.

    Science.gov (United States)

    Black Hawk Coll., Moline, IL.

    An advisory committee is generally comprised of persons outside the education profession who have specialized knowledge in a given area. The committee advises, makes recommendations, and gives service to the college and its students, instructors, and administrators. At Black Hawk College, there are four types of advisory committees: community,…

  3. Inter-Society Research Committee

    International Nuclear Information System (INIS)

    Akiyama, Mamoru; Higuchi, Masahisa.

    1996-01-01

    World-wide tendencies and circumstances for nuclear power cannot be said to be moving full of sail with a favorable wind, due to nuclear power plant accidents and comparatively little economical benefit. The present Nuclear Power Plant situation is that some personnel understand a need for the development from the viewpoint of efficient energy usage in the world and environmental problems like global warming. At the same time others oppose future nuclear development from the viewpoint of safety problems and economic cost. These issues may end nuclear development worldwide. Nuclear development must be considered from an international viewpoint and other various aspects. Therefore, all countries concerned should cooperative in the adjustment of research carried out by each country. Nuclear power's future must be efficient in the utilization of limited resources (money, manpower and facilities). It is concluded that the ISRC should only discuss technical matters on nuclear engineering, independent from political influence. Societies agreeing to this idea, provide the ISRC with money and/or manpower and/or facilities. The ISRC will consist of a research program committee and research task forces. Members of the Research Program Committee are the chairmen of the research task forces who are also society representatives. The Committee will discuss research programs and resources. The research task forces will consist of one society representative chairman and specialists on the program

  4. 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

  5. Design Evolution Study - Aging Options

    International Nuclear Information System (INIS)

    McDaniel, P.

    2002-01-01

    The purpose of this study is to identify options and issues for aging commercial spent nuclear fuel received for disposal at the Yucca Mountain Mined Geologic Repository. Some early shipments of commercial spent nuclear fuel to the repository may be received with high-heat-output (younger) fuel assemblies that will need to be managed to meet thermal goals for emplacement. The capability to age as much as 40,000 metric tons of heavy metal of commercial spent nuclear he1 would provide more flexibility in the design to manage this younger fuel and to decouple waste receipt and waste emplacement. The following potential aging location options are evaluated: (1) Surface aging at four locations near the North Portal; (2) Subsurface aging in the permanent emplacement drifts; and (3) Subsurface aging in a new subsurface area. The following aging container options are evaluated: (1) Complete Waste Package; (2) Stainless Steel inner liner of the waste package; (3) Dual Purpose Canisters; (4) Multi-Purpose Canisters; and (5) New disposable canister for uncanistered commercial spent nuclear fuel. Each option is compared to a ''Base Case,'' which is the expected normal waste packaging process without aging. A Value Engineering approach is used to score each option against nine technical criteria and rank the options. Open issues with each of the options and suggested future actions are also presented. Costs for aging containers and aging locations are evaluated separately. Capital costs are developed for direct costs and distributable field costs. To the extent practical, unit costs are presented. Indirect costs, operating costs, and total system life cycle costs will be evaluated outside of this study. Three recommendations for aging commercial spent nuclear fuel--subsurface, surface, and combined surface and subsurface are presented for further review in the overall design re-evaluation effort. Options that were evaluated but not recommended are: subsurface aging in a new

  6. Reasons for the nuclear power option

    International Nuclear Information System (INIS)

    Rotaru, I.; Glodeanu, F.; Mauna, T.

    1994-01-01

    Technical, economical and social reasons, strongly supporting the nuclear power option are reviewed. The history of Romanian nuclear power program is outlined with a particular focus on the Cernavoda Nuclear Power Plant project. Finally the prospective of nuclear power in Romania are assessed

  7. Low-level radioactive waste management options

    International Nuclear Information System (INIS)

    Schmalz, R.F.

    1989-01-01

    This paper discusses the non-technical problems associated with the social and political obstacles to the secure disposal of low level radioactive waste. The author reviews thirty years' experience managing non-military wastes. The merits of available options are considered

  8. Perspectives for the provision of biofuels. Classification of fuel options according to technical, economic and ecological criteria; Perspektiven der Biokraftstoffbereitstellung. Einordnung der Kraftstoffoptionen nach technischen, oekonomischen und oekologischen Kriterien

    Energy Technology Data Exchange (ETDEWEB)

    Scheftelowitz, Mattes; Mueller-Langer, Franziska [DBFZ Deutsches BiomasseForschungsZentrum gemeinnuetzige GmbH, Leipzig (Germany)

    2009-07-01

    Next to the use of more efficient, innovative technologies (including hybrid vehicles, electromobility) another important contribution to reducing greenhouse gas emissions in the traffic sector will have to come from biofuels. A wide variety of conversion pathways, each with numerous process alternatives, is available along the whole length of the ''well-to-wheel'' chain (i.e. starting from biomass cropping or recovery, through its supply and conversion to biofuel, including the necessary infrastructure, and ending with its final use). The present paper presents various biofuel options and compares them on the basis of systematic, economic and ecological criteria.

  9. Traditional preventive treatment options

    DEFF Research Database (Denmark)

    Longbottom, C; Ekstrand, K; Zero, D

    2009-01-01

    Preventive treatment options can be divided into primary, secondary and tertiary prevention techniques, which can involve patient- or professionally applied methods. These include: oral hygiene (instruction), pit and fissure sealants ('temporary' or 'permanent'), fluoride applications (patient...... options....

  10. Breast Cancer: Treatment Options

    Science.gov (United States)

    ... Breast Cancer > Breast Cancer: Treatment Options Request Permissions Breast Cancer: Treatment Options Approved by the Cancer.Net Editorial ... can be addressed as quickly as possible. Recurrent breast cancer If the cancer does return after treatment for ...

  11. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

    Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

  12. Distributed Energy Implementation Options

    Energy Technology Data Exchange (ETDEWEB)

    Shah, Chandralata N [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-09-13

    This presentation covers the options for implementing distributed energy projects. It distinguishes between options available for distributed energy that is government owned versus privately owned, with a focus on the privately owned options including Energy Savings Performance Contract Energy Sales Agreements (ESPC ESAs). The presentation covers the new ESPC ESA Toolkit and other Federal Energy Management Program resources.

  13. Nuclear risk management on stage: a decision analysis perspective on the UK's Committee on Radioactive Waste Management.

    Science.gov (United States)

    Morton, Alec; Airoldi, Mara; Phillips, Lawrence D

    2009-05-01

    In 2003, the UK government set up a broad-based Committee on radioactive waste management (CoRWM) to look at the UK's policy on radioactive waste management with a view to jumpstarting a stalled policy process. The committee's brief was to come up with a set of recommendations that would protect the public and the environment, and be capable of inspiring public confidence. After consulting widely with the public and stakeholders, and drawing on advice from scientists and other experts, CoRWM arrived at a remarkably well-received set of recommendations. On the basis of our experiences of working on CoRWM's multi-criteria decision analysis of different management options, study of CoRWM documentation, and interviews with committee members, we describe the explicit and implicit principles that guided CoRWM. We also give an account of the process by which CoRWM arrived at its conclusions, covering four phases: framing, shortlisting, option assessment, and integration; and four cross-cutting activities: public and stakeholder engagement (PSE), science and engineering input, ethics and social science input, and learning from overseas practice. We finish by outlining some of the key developments in the UK's radioactive waste management process, which followed on from the publication of CoRWM's report, and present our reflections for the benefit of the risk and decision analysts of future committees that, like CoRWM, are charged with recommending to government on the management of technically complex and risky technologies, drawing on extensive public and stakeholder consultation.

  14. Options For The Disposition Of UK Civil Plutonium Stocks

    Energy Technology Data Exchange (ETDEWEB)

    Moore, R.G.; Zimmerman, C.H.; Scales, C.; Worrall, A.; Sims, H.E.; Fowler, L. [Nexia Solutions Ltd (United Kingdom)

    2008-07-01

    The UK Civil Pu Disposition project will identify and assess the viability of several technical options for dealing with the UK's civil separated Pu stockpile and the discriminators that will support technology option down-selection decisions. The overall aim will be to deliver feasible technical options and comprehensive information on political, economic, sociological, environmental and technical factors for each strategic option. This paper briefly describes the work completed to date to assess immobilisation and re-use technologies as disposition strategies and on the work that will identify discriminators to support technology down-selection. The Pu disposition project is anticipated to continue for several years while the necessary investigations are made to fully understand the various options. The work planned over this period is discussed. (authors)

  15. Options For The Disposition Of UK Civil Plutonium Stocks

    International Nuclear Information System (INIS)

    Moore, R.G.; Zimmerman, C.H.; Scales, C.; Worrall, A.; Sims, H.E.; Fowler, L.

    2008-01-01

    The UK Civil Pu Disposition project will identify and assess the viability of several technical options for dealing with the UK's civil separated Pu stockpile and the discriminators that will support technology option down-selection decisions. The overall aim will be to deliver feasible technical options and comprehensive information on political, economic, sociological, environmental and technical factors for each strategic option. This paper briefly describes the work completed to date to assess immobilisation and re-use technologies as disposition strategies and on the work that will identify discriminators to support technology down-selection. The Pu disposition project is anticipated to continue for several years while the necessary investigations are made to fully understand the various options. The work planned over this period is discussed. (authors)

  16. Ethics committees in Italy--a time for change?

    Science.gov (United States)

    Wray, E

    2000-01-01

    The Comitato Nazionale per la Bioetica (CNB) in Italy has recently produced an unprecedented discussion document on the state of ethics committees in Italy, with an invitation to interested parties to comment on proposed changes to their fundamental structure. After this consultation, and taking note of relevant official publications and the most recent national and international literature on the subject, the CNB proposes to produce a final, definitive document that will consider options for the future development of such committees.

  17. Energy in transition, 1985-2010. Final report of the Committee on Nuclear and Alternative Energy Systems, National Research Council

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    This exhaustive study, in assessing the roles of nuclear and alternative energy systems in the nation's energy future, focuses on the period between 1985 and 2010. Its intent is to illuminate the kinds of options the nation may wish to keep open in the future and to describe the actions, policies, and R and D programs that may be required to do so. The timing and the context of these decisions depend not only on the technical, social, and economic features of energy-supply technologies, but also on assumptions about future demand for energy and the possibilities for energy conservation through changes in consumption patterns and improved efficiency of the supply and end-use systems. The committee developed a three-tiered functional structure for the project. The first tier was CONAES itself, whose report embodies the ultimate findings, conclusions, and judgments of the study. To provide scientific and engineering data and economic analyses for the committee, a second tier of four panels was appointed by the committee to examine (1) energy demand and conservation, (2) energy supply and delivery systems, (3) risks and impacts of energy supply and use, and (4) various models of possible future energy systems and decision making. Each panel in turn established a number of resource groups - some two dozen in all - to address in detail an array of more particular matters. Briefly stated, recommended strategies are: (1) increased energy conservation; (2) expansion of the nation's balanced coal and nuclear electrical generation base; (3) retention of the breeder option; (4) stimulation of fluid energy development; and (5) immediate increase in research and development of new energy options to ensure availability over the long term.

  18. TANK SPACE OPTIONS REPORT

    International Nuclear Information System (INIS)

    Willis, W.L.; Ahrendt, M.R.

    2009-01-01

    Since this report was originally issued in 2001, several options proposed for increasing double-shell tank (DST) storage space were implemented or are in the process of implementation. Changes to the single-shell tank (SST) waste retrieval schedule, completion of DST space saving options, and the DST space saving options in progress have delayed the projected shortfall of DST storage space from the 2007-2011 to the 2018-2025 timeframe (ORP-11242, River Protection Project System Plan). This report reevaluates options from Rev. 0 and includes evaluations of new options for alleviating projected restrictions on SST waste retrieval beginning in 2018 because of the lack of DST storage space.

  19. Electricity by anaerobic digestion of vinasse from sugar cane. Technical profile, economic and environmental impacts of an option; Eletricidade por digestao anaerobia da vinhaca de cana-de-acucar. Contornos tecnicos, economicos e ambientais de uma opcao

    Energy Technology Data Exchange (ETDEWEB)

    Rego, Erik Eduardo; Moral Hernandez, Francisco del [Universidade de Sao Paulo (PIPGE/IEE/USP), SP (Brazil). Inst. de Eletrotecnica e Energia. Programa Interunidades de Pos-Graduacao em Energia

    2006-07-01

    In its first part this article brings up the growing importance of biomass in Brazilian and within the world energy scenario, especially due to the higher environmental consciousness related to the use of renewable energy sources. It also discusses about biomass sustainability and its myths. The Brazilian case shows that the usage of biomass is mixed to the use of sugar cane. The studies in this area are essentially directed to the production of ethanol and the burn of the solid waste production in steam generators. This article focuses on a specific liquid effluent product: the vinasse. The use of vinasse in agriculture as liquid fertilizer is not new. This article studies the technical, economical and environmental viability of the biogas production obtained from the anaerobic digestion of vinasse in order to generate electricity. The reactor under analysis is the UASB (Upflow Anaerobic Sludge Blanket) and a case study of a experimental process linked to alcohol production is used as a base to put side by side some points of view. Finally this article discusses how environmental regulations related to the effluent disposal (and their differences between two states in Brazil) were really trade-off issues in the decision making from the economical perspective. The combinations of the analysis (technical, economical and environmental) contributes for the global dimension of the alternative. (author)

  20. Evaluating Space Weather Architecture Options to Support Human Deep Space Exploration of the Moon and Mars

    Science.gov (United States)

    Parker, L.; Minow, J.; Pulkkinen, A.; Fry, D.; Semones, E.; Allen, J.; St Cyr, C.; Mertens, C.; Jun, I.; Onsager, T.; Hock, R.

    2018-02-01

    NASA's Engineering and Space Center (NESC) is conducting an independent technical assessment of space environment monitoring and forecasting architecture options to support human and robotic deep space exploration.

  1. 78 FR 69991 - Advisory Committee; Veterinary Medicine Advisory Committee; Termination

    Science.gov (United States)

    2013-11-22

    .... FDA-2013-N-1380] Advisory Committee; Veterinary Medicine Advisory Committee; Termination AGENCY: Food... announcing the termination of the Veterinary Medicine Advisory Committee. This document removes the Veterinary Advisory Committee from the Agency's list of standing advisory committees. DATES: This rule is...

  2. Evolution of IEC/TC 45 works and its sub-committees from 1960 to 1983

    International Nuclear Information System (INIS)

    Weill, J.

    1983-10-01

    The IEC, founded in 1906, is an independent international standards organization. Its standardization work deals with almost all branches of electrotechnology in the electrotechnical, electronical and data-processing field, covering all applications, as for example telecommunications and nuclear energy. The IEC Central Office is situated in Geneva (Switzerland). The Technical Committee No. 45 was set up in 1960 at the IEC general meeting in New Delhi, with the scope as given in the IEC Directory. Its revised scope is under consideration in the Committee of Action of the IEC and reads: ''To prepare international standards relating to electrical and electronic equipment and systems specific to nuclear applications''. The chart shows the organigram of the Technical Committee which comprises about 75 experts in the nuclear field from about 20 industrial countries. We can see here the standard diagram of a Technical Committee with its Sub-committees and Working Groups. The meetings are held in a member country at the request of its National Committee. One shows the places of the plenary meetings of TC 45 as well as the meetings of its Sub-committees and their Working Groups held till now. The Technical Committee 45 has in addition to its seven Working Groups also two Sub-committees having several further Working Groups of their own. The Sub-committee 45 A ''Reactor Instrumentation''. The Sub-committee 45 B ''Radiation protection instrumentation''. Till now TC 45 has published about 85 standards. Regarding work in preparation, one shows the present and future work within the Technical Committee and its Sub-committees. Impact of works and liaisons is briefly discussed [fr

  3. Report on the third meeting of the project advisory committee (technical) for IAEA/WHO Project EGY/6/004 (Egyptian Cancer Project) 27-29 April 1985, at NEMROCK, Cairo. PACT(3)

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1985-06-01

    The Project was launched in March 1983, with the first meeting of the Committee (PACT(I)). It was planned for a duration of four years. Now, after two years experience, PACT(III) met to review results so far and to advise on actions for the remaining two years. Appendix 1 lists those present at the meeting. Since 1983 a Pilot Project has been running at NEMROCK, the Nuclear Medicine and Radiation Oncology Centre at Cairo University Hospital, at which the Project is based. Two training courses have been given, in November 1983 and November 1984, and treatment has been given using protocols developed under the project. PACT(III) examined clinical results obtained so far and made recommendations for the extension of the scheme to other hospitals in Egypt

  4. Report to the DOE Nuclear Data Committee

    International Nuclear Information System (INIS)

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

    1981-04-01

    This report was prepared for the DOE Nuclear Data Committee, and covers work performed at ORNL since April 1980 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 has been reproduced with only minor editing. In a few cases progress reports were written specifically for this publication. The editors have selected the material to be included in this report on the basis of perceived interests of DOE Nuclear Data Committee members

  5. AEC Advisory Committee report emphasizes personnel exchanges

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The Advisory Committee on Cooperation with Developing Countries set up in August 1983 in the AEC has studied for about one year the actual situations of nuclear energy development and utilization in developing countries and their expections toward Japan and also problems in Japan in this connection. The Advisory Committee's report is summarized: significance of nuclear energy cooperation; status of nuclear energy energy utilizations in developing countries; status and problems in Japan's cooperation (technical cooperation through IAEA and technical cooperation by JAERI, JAIF, etc.); future prospects (areas of cooperation including the uses of radioisotopes and radiation and research reactors, nuclear power generation, etc. and tasks of the Government and the private sector in expanding the cooperation). (Mori, K.)

  6. 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

  7. [Responsibilities of ethics committees].

    Science.gov (United States)

    von Bergmann, K

    2000-05-01

    Increasing numbers of clinical research projects are submitted to ethical committees (institutional review boards) for approval. New therapeutic developments have to be evaluated by these committees to protect patients/volunteers. Thus, the responsibility of ethical committees is increasing. The "Nürnberger Kodex" and the "Declaration of Helsinki" are the background for these evaluations. According to the German drug law the physician is obligated by law to submit the protocol to such a committee. In addition, local state physician authorities require such a procedure. Important considerations during the review process besides ethical aspects are the informed consent, which should be written in an understandable form, and the obligations of the insurance.

  8. Consensus, contracts, and committees.

    Science.gov (United States)

    Moreno, J D

    1991-08-01

    Following a brief account of the puzzle that ethics committees present for the Western Philosophical tradition, I will examine the possibility that social contract theory can contribute to a philosophical account of these committees. Passing through classical as well as contemporary theories, particularly Rawls' recent constructivist approach, I will argue that social contract theory places severe constraints on the authority that may legitimately be granted to ethics committees. This, I conclude, speaks more about the suitability of the theory to this level of analysis than about the ethics committee phenomenon itself.

  9. Response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. Proceedings of a technical committee meeting held in Beijing, China, 25-27 October 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    The meeting was convened by the IAEA on the recommendation of the IAEA`s International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Netherlands, Switzerland, the Russian Federation, the United Kingdom and the United States of America. The meeting covered the following topics: experimental investigations of the effects of air and water ingress; predicted response of fuel, graphite and other reactor components; options for minimizing or mitigating the effects of air or water ingress. 19 papers were presented at the meeting. A separate abstract was prepared for each of these papers. Refs, figs and tabs.

  10. Management options for recycling radioactive scrap metals

    Energy Technology Data Exchange (ETDEWEB)

    Dehmel, J.C.; MacKinney, J.; Bartlett, J.

    1997-02-01

    The feasibility and advantages of recycling radioactive scrap metals (RSM) have yet to be assessed, given the unique technical, regulatory, safety, and cost-benefit issues that have already been raised by a concerned recycling industry. As is known, this industry has been repeatedly involved with the accidental recycling of radioactive sources and, in some cases, with costly consequences. If recycling were deemed to be a viable option, it might have to be implemented with regulatory monitoring and controls. Its implementation may have to consider various and complex issues and address the requirements and concerns of distinctly different industries. There are three basic options for the recycling of such scraps. They are: (1) recycling through the existing network of metal-scrap dealers and brokers, (2) recycling directly and only with specific steelmills, or (3) recycling through regional processing centers. Under the first option, scrap dealers and brokers would receive material from RSM generators and determine at which steelmills such scraps would be recycled. For the second option, RSM generators would deal directly with selected steelmills under specific agreements. For the third option, generators would ship scraps only to regional centers for processing and shipment to participating steelmills. This paper addresses the potential advantages of each option, identifies the types of arrangements that would need to be secured among all parties, and attempts to assess the receptivity of the recycling industry to each option.

  11. Non-burn electric generation: How today's options stack up

    International Nuclear Information System (INIS)

    1993-01-01

    The technical preparedness to generate electricity without burning fuel is dealt with. Nuclear, hydroelectric, solar and wind energy are recommended as the clean options. The aims of energy policy, views upon regulation, technical maturity and commercial preparedness of such variants are discussed. (Z.S.). 4 figs

  12. Committee on Science

    Science.gov (United States)

    SCIENCE ADVISOR WASHINGTON, DC -- Today, House Science Committee Chairman Sherwood Boehlert (R-NY23) and Advisor nominee Dr. John H. Marburger. The Senate Commerce Committee has scheduled a nomination hearing for this afternoon, and Boehlert and Grucci have been invited to testify. Dr. Marburger was nominated

  13. LOCAL ORGANIZING COMMITTEE

    Indian Academy of Sciences (India)

    Prof. B. B. P. Gupta

    INDIAN ACADEMY OF SCIENCES. Bengaluru. 83rd ANNUAL MEETING. 3–5 November 2017, NEHU, Shillong. LOCAL ORGANIZING COMMITTEE. Local Organizing Committee. 1. Prof. S. K. Srivastava. Chairman. Vice-Chancellor, NEHU, Shillong. 2. Prof. B. B. P. Gupta. Organising Secretary. Department of Zoology ...

  14. Policy options for stabilizing global climate

    International Nuclear Information System (INIS)

    Lashof, D.A.; Tirpak, D.A.

    1990-12-01

    This report to congress by the US EPA explains the greenhouse effect and its influence on global climate. It outlines the trends in the greenhouse gases - their concentration history, distribution, sources and sinks and chemical and radiative properties. Climate change processes are discussed including climate feedbacks. Human activities affecting trace gases and climate are explained, followed by a chapter on the technical options for reducing greenhouse gas emissions which looks at energy services, energy supply, industry, forestry and agriculture. The future is considered, and the final chapters are concerned with policy options and international cooperation to reduce greenhouse gas emissions. 934 refs., 102 figs., 84 tabs

  15. Pesticide Program Dialogue Committee (PPDC)

    Science.gov (United States)

    The Pesticide Program Dialogue Committee, a permanent, broadly representative advisory committee, meets with EPA on a regular basis to discuss pesticide regulatory, policy, and program implementation issues.

  16. The origins of options.

    Science.gov (United States)

    Smaldino, Paul E; Richerson, Peter J

    2012-01-01

    Most research on decision making has focused on how human or animal decision makers choose between two or more options, posed in advance by the researchers. The mechanisms by which options are generated for most decisions, however, are not well understood. Models of sequential search have examined the trade-off between continued exploration and choosing one's current best option, but still cannot explain the processes by which new options are generated. We argue that understanding the origins of options is a crucial but untapped area for decision making research. We explore a number of factors which influence the generation of options, which fall broadly into two categories: psycho-biological and socio-cultural. The former category includes factors such as perceptual biases and associative memory networks. The latter category relies on the incredible human capacity for culture and social learning, which doubtless shape not only our choices but the options available for choice. Our intention is to start a discussion that brings us closer toward understanding the origins of options.

  17. Americal options analyzed differently

    NARCIS (Netherlands)

    Nieuwenhuis, J.W.

    2003-01-01

    In this note we analyze in a discrete-time context and with a finite outcome space American options starting with the idea that every tradable should be a martingale under a certain measure. We believe that in this way American options become more understandable to people with a good working

  18. Traffic Light Options

    DEFF Research Database (Denmark)

    Jørgensen, Peter Løchte

    This paper introduces, prices, and analyzes traffic light options. The traffic light option is an innovative structured OTC derivative developed independently by several London-based investment banks to suit the needs of Danish life and pension (L&P) companies, which must comply with the traffic...... 2006, and supervisory authorities in many other European countries have implemented similar regulation. Traffic light options are therefore likely to attract the attention of a wider audience of pension fund managers in the future. Focusing on the valuation of the traffic light option we set up a Black...... light scenarios. These stress scenarios entail drops in interest rates as well as in stock prices, and traffic light options are thus designed to pay off and preserve sufficient capital when interest rates and stock prices fall simultaneously. Sweden's FSA implemented a traffic light system in January...

  19. Traffic Light Options

    DEFF Research Database (Denmark)

    Jørgensen, Peter Løchte

    2007-01-01

    This paper introduces, prices, and analyzes traffic light options. The traffic light option is an innovative structured OTC derivative developed independently by several London-based investment banks to suit the needs of Danish life and pension (L&P) companies, which must comply with the traffic...... 2006, and supervisory authorities in many other European countries have implemented similar regulation. Traffic light options are therefore likely to attract the attention of a wider audience of pension fund managers in the future. Focusing on the valuation of the traffic light option we set up a Black...... light scenarios. These stress scenarios entail drops in interest rates as well as in stock prices, and traffic light options are thus designed to pay off and preserve sufficient capital when interest rates and stock prices fall simultaneously. Sweden's FSA implemented a traffic light system in January...

  20. Imagining Technicities

    DEFF Research Database (Denmark)

    Liboriussen, Bjarke; Plesner, Ursula

    2011-01-01

    to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

  1. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  3. Moderator Configuration Options for ESS

    DEFF Research Database (Denmark)

    Zanini, L.; Batkov, K.; Klinkby, Esben Bryndt

    2016-01-01

    The current, still evolving status of the design and the optimization work for the moderator configuration for the European Spallation Source is described. The moderator design has been strongly driven by the low-dimensional moderator concept recently proposed for use in spallation neutron sources...... or reactors. Quasi-two dimensional, disc- or tube-shaped moderators,can provide strong brightness increase (factor of 3 or more) with respect to volume para-H2moderators, which constitute the reference, state-of-the-art technology for high-intensity coupled moderators. In the design process other, more...... conventional, principles were also considered,such as the importance of moderator positioning, of the premoderator, and beam extraction considerations. Different design and configuration options are evaluated and compared with the reference volume moderator configuration described in the ESS Technical Design...

  4. Options Study Documenting the Fast Reactor Fuels Innovative Design Activity

    Energy Technology Data Exchange (ETDEWEB)

    Jon Carmack; Kemal Pasamehmetoglu

    2010-07-01

    This document provides presentation and general analysis of innovative design concepts submitted to the FCRD Advanced Fuels Campaign by nine national laboratory teams as part of the Innovative Transmutation Fuels Concepts Call for Proposals issued on October 15, 2009 (Appendix A). Twenty one whitepapers were received and evaluated by an independent technical review committee.

  5. Polish Toxic Currency Options

    Directory of Open Access Journals (Sweden)

    Waldemar Gontarski

    2009-06-01

    Full Text Available Toxic currency options are defined on the basis of the opposition to the nature (essence of an option contract, which is justified in terms of norms founded on the general law clause of characteristics (nature of a relation (which represents an independent premise for imposing restrictions on the freedom of contracts. So-understood toxic currency options are unlawful. Indeed they contravene iuris cogentis regulations. These include for instance option contracts, which are concluded with a bank, if the bank has not informed about option risk before concluding the contract; or the barrier options, which focus only on the protection of bank’s interests. Therefore, such options may appear to be invalid. Therefore, performing contracts for toxic currency options may be qualified as a criminal mismanagement. For the sake of security, the manager should then take into consideration filing a claim for stating invalidity (which can be made in a court verdict. At the same time, if the supervisory board member in a commercial company, who can also be a subject to mismanagement offences, commits an omission involving lack of reaction (for example, if he/she fails to notify of the suspected offence committed by the management board members acting to the company’s detriment when the management board makes the company conclude option contracts which are charged with absolute invalidity the supervisory board member so acting may be considered to act to the company’s detriment. In the most recent Polish jurisprudence and judicature the standard of a “good host” is treated to be the last resort for determining whether the manager’s powers resulting from criminal regulations were performed. The manager of the exporter should not, as a rule, issue any options. Issuing options always means assuming an obligation. In the case of currency put options it is an absolute obligation to purchase a given amount in euro at exchange rate set in advance. On the

  6. 2005 resource options report

    International Nuclear Information System (INIS)

    Morris, T.

    2005-01-01

    This resource options report (ROR) fulfils regulatory requirements in British Columbia's two-year resource planning process. It identifies a wide range of resources and technologies that could be used to meet BC Hydro's future electricity demand. As such, it facilitates a transparent public review of resource options which include both supply-side and demand-side options. The resource options that will be used in the 2005 integrated electricity plan (IEP) were characterized. This ROR also documents where there is a general agreement or disagreement on the resource type characterization, based on the First Nations and Stakeholder engagement. BC Hydro used current information to provide realistic ranges on volume and cost to characterize environmental and social attributes. The BC Hydro system was modelled to assess the benefit and cost of various resource options. The information resulting from this ROR and IEP will help in making decisions on how to structure competitive acquisition calls and to determine the level of transmission services needed to advance certain BC Hydro projects. The IEP forecasts the nature and quantity of domestic resources required over the next 20 years. A strategic direction on how those needs will be met has been created to guide the management of BC Hydro's energy resources. Supply-side options include near-commercial technologies such as energy storage, ocean waves, tidal, fuel cells and integrated coal gasification combined cycle technology. Supply-side options also include natural gas, coal, biomass, geothermal, wind, and hydro. 120 refs., 39 tabs., 21 figs., 6 appendices

  7. Expensing options solves nothing.

    Science.gov (United States)

    Sahlman, William A

    2002-12-01

    The use of stock options for executive compensation has become a lightning rod for public anger, and it's easy to see why. Many top executives grew hugely rich on the back of the gains they made on their options, profits they've been able to keep even as the value they were supposed to create disappeared. The supposed scam works like this: Current accounting regulations let companies ignore the cost of option grants on their income statements, so they can award valuable option packages without affecting reported earnings. Not charging the cost of the grants supposedly leads to overstated earnings, which purportedly translate into unrealistically high share prices, permitting top executives to realize big gains when they exercise their options. If an accounting anomaly is the problem, then the solution seems obvious: Write off executive share options against the current year's revenues. The trouble is, Sahlman writes, expensing option grants won't give us a more accurate view of earnings, won't add any information not already included in the financial statements, and won't even lead to equal treatment of different forms of executive pay. Far worse, expensing evades the real issue, which is whether compensation (options and other-wise) does what it's supposed to do--namely, help a company recruit, retain, and provide the right people with appropriate performance incentives. Any performance-based compensation system has the potential to encourage cheating. Only ethical management, sensible governance, adequate internal control systems, and comprehensive disclosure will save the investor from disaster. If, Sahlman warns, we pass laws that require the expensing of options, thinking that's fixed the fundamental flaws in corporate America's accounting, we will have missed a golden opportunity to focus on the much more extensive defects in the present system.

  8. Self-healing phenomena in cement-based materials state-of-the-art report of RILEM Technical Committee 221-SHC Self-Healing Phenomena in Cement-Based Materials

    CERN Document Server

    Tittelboom, Kim; Belie, Nele; Schlangen, Erik

    2013-01-01

    Self-healing materials are man-made materials which have the built-in capability to repair damage. Failure in materials is often caused by the occurrence of small microcracks throughout the material. In self-healing materials phenomena are triggered to counteract these microcracks. These processes are ideally triggered by the occurrence of damage itself. Thus far, the self-healing capacity of cement-based materials has been considered as something "extra". This could be called passive self-healing, since it was not a designed feature of the material, but an inherent property of it. Centuries-old buildings have been said to have survived these centuries because of the inherent self-healing capacity of the binders used for cementing building blocks together. In this State-of-the-Art Report a closer look is taken at self-healing phenomena in cement-based materials. It is shown what options are available to design for this effect rather than have it occur as a "coincidental extra".

  9. Nuclear spent fuel management. Experience and options

    International Nuclear Information System (INIS)

    1986-01-01

    Spent nuclear fuel can be stored safely for long periods at relatively low cost, but some form of permanent disposal will eventually be necessary. This report examines the options for spent fuel management, explores the future prospects for each stage of the back-end of the fuel cycle and provides a thorough review of past experience and the technical status of the alternatives. Current policies and practices in twelve OECD countries are surveyed

  10. Disposal options for radioactive waste

    International Nuclear Information System (INIS)

    Olivier, J.P.

    1991-01-01

    On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

  11. Early Option Exercise

    DEFF Research Database (Denmark)

    Heje Pedersen, Lasse; Jensen, Mads Vestergaard

    A classic result by Merton (1973) is that, except just before expiration or dividend payments, one should never exercise a call option and never convert a convertible bond. We show theoretically that this result is overturned when investors face frictions. Early option exercise can be optimal when...... it reduces short-sale costs, transaction costs, or funding costs. We provide consistent empirical evidence, documenting billions of dollars of early exercise for options and convertible bonds using unique data on actual exercise decisions and frictions. Our model can explain as much as 98% of early exercises...

  12. Early Option Exercise

    DEFF Research Database (Denmark)

    Jensen, Mads Vestergaard; Heje Pedersen, Lasse

    2016-01-01

    A classic result by Merton (1973) is that, except just before expiration or dividend payments, one should never exercise a call option and never convert a convertible bond. We show theoretically that this result is overturned when investors face frictions. Early option exercise can be optimal when...... it reduces short-sale costs, transaction costs, or funding costs. We provide consistent empirical evidence, documenting billions of dollars of early exercise for options and convertible bonds using unique data on actual exercise decisions and frictions. Our model can explain as much as 98% of early exercises...

  13. Potential Fit to the Department Outweighs Professional Criteria in the Hiring Process in Academic Libraries. A Review of: Wang, Z. & Guarria, C. (2010. Unlocking the mystery: What academic library search committees look for in filling faculty positions. Technical Services Quarterly, 27, 66–86.

    Directory of Open Access Journals (Sweden)

    Yvonne Hultman Özek

    2010-12-01

    Full Text Available Objective – To identify key factors affecting the probability of obtaining an interview and being hired for an academic library position.Design – An online survey was distributed via the following electronic mail lists: ACRL, LITA, COLLIB, METRO, ACQNET, COLLDV, ULS, EQUILIBR, and ALF. The questionnaire was posted via StudentVoice, an assessment survey provider.Setting – Academic libraries in the United States.Subjects – The 242 academic library search committees that responded to the online survey.Methods – The authors reviewed the literature on the hiring process in academic libraries. A questionnaire for an online survey was developed. The instrument contained closed questions with the option to add comments. The survey was available for completion June 3 to June 15, 2008.Main Results – Skills and performance of job requirements were rated as the most important criteria by 90% of the 242 academic library search committees that responded to the survey. Previous academic library experience was rated as essential by 38%. The findings also showed that committees are positive towards hiring recent graduates, and over 90% check references. In addition, 75% of the respondents emphasized the importance of skills in bibliographic instruction (BI, particularly when choosing staff for public services.Furthermore, of the 242 respondents, 47.52%, answering the corresponding question indicated that a relevant cover letter, correct spelling, and declaration of the candidate’s activities over all time periods are crucial aspects.Those in favour of using a weighted scoring system, 37% of 218 respondents, felt that it served as a tool to level the playing field for gathering accurate information, and it also helped to improve the efficiency as well as speed of the hiring process. However, 62.84% of the respondents commented that a weighted scoring system is too prescribed, and some universities did not allow the use of this method. Of 218

  14. Standing Concertation Committee

    CERN Document Server

    HR Department

    2008-01-01

    ORDINARY MEETING ON 27 FEBRUARY 2008 The main items discussed at the meetings of the Standing Concertation Committee on 27 February 2008 included: Short-term Saved Leave Scheme The Committee noted that, by the end of February 2008, some 600 staff had enrolled in the short-term saved leave scheme: approx. 58% had signed up for 1 slice, 14% for two slices, 5% for three slices and 23% for four slices. Administrative Circular No. 4 (Rev. 4) - Unemployment Insurance Scheme The Committee agreed to recommend the Director-General to approve Administrative Circular No. 4 (Rev. 4) - Unemployment Insurance Scheme. Administrative Circular No. 30 (Rev. 2) - Financial benefits upon taking up appointment and termination of contract The Committee agreed to recommend the Director-General to approve Administrative Circular No. 30 (Rev. 2) - Financial Benefits upon taking up appointment and termination of contract. Progressive Retirement Programme The Progressive Retirement Programme (PR...

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

    International Nuclear Information System (INIS)

    Martinelli, R.

    1991-01-01

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

  16. Security option file - Exploitation (DOS-Expl)

    International Nuclear Information System (INIS)

    2016-01-01

    This document aims at presenting functions performed by Cigeo during its exploitation phase, its main technical and security options which are envisaged with respect to different types of internal or external risks, and a first assessment of its impact on mankind and on the environment during its exploitation in normal operation as well as in incidental or accidental situations. A first volume addresses security principles, approach and management in relationship with the legal and regulatory framework. The second volume presents input data related to waste parcels and used for the installation sizing and operation, the main site characteristics, the main technical options regarding structures and equipment, and the main options regarding exploitation (parcel management, organisational and human aspects, and effluent management). The third volume describes how parcel are processed from their arrival to their setting in storage compartment, an inventory of internal and external risks, and a first assessment of consequences of scenarios on mankind and on the environment. The fourth volume presents options and operations which are envisaged regarding Cigeo closure, and inventory of associated risks

  17. Thermometers: Understand the Options

    Science.gov (United States)

    ... the options Thermometers come in a variety of styles. Understand the different types of thermometers and how ... MA. Fever in infants and children: Pathophysiology and management. http://www.uptodate.com/home. Accessed July 23, ...

  18. Options for human intrusion

    International Nuclear Information System (INIS)

    Bauser, M.; Williams, R.

    1993-01-01

    This paper addresses options for dealing with human intrusion in terms of performance requirements and repository siting and design requirements. Options are presented, along with the advantages and disadvantages of certain approaches. At the conclusion, a conceptual approach is offered emphasizing both the minimization of subjective judgements concerning future human activity, and specification of repository requirements to minimize the likelihood of human intrusion and any resulting, harmful effects should intrusion occur

  19. Radioactive waste: the Nuclear Industry's response to the Environment Committee's report

    International Nuclear Information System (INIS)

    1986-07-01

    This paper represents the nuclear industry's response to the Environmental Committee's report on the handling and disposal of radioactive wastes. Topics covered include the historical aspects of the management of radioactive wastes, technical problems, comparisons with overseas management methods, liquid effluents, reprocessing problems, and public attitudes and perceptions of radioactive waste. Responses to the Environmental Committee's recommendations form an appendix. (U.K.)

  20. 21 CFR 14.171 - Utilization of an advisory committee on the initiative of FDA.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Utilization of an advisory committee on the initiative of FDA. 14.171 Section 14.171 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH... technical advisory committee for human prescription drugs. The Commissioner's determinations on the agenda...

  1. 76 FR 3684 - Self-Regulatory Organizations; The Options Clearing Corporation; Order Granting Approval of...

    Science.gov (United States)

    2011-01-20

    ... SECURITIES AND EXCHANGE COMMISSION [Release No. 34-63711; File No. SR-ODD-2011-01] Self-Regulatory... to the Options Disclosure Document Reflecting Certain Changes to Disclosure Regarding Credit Default Options in, and Making Certain Technical Amendments to, the June 2007 Supplement to the Options Disclosure...

  2. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  3. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the purpose of devices connected to the TN and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  4. 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

  5. Ethics committees in India: Facing the challenges!

    Science.gov (United States)

    Kadam, Rashmi; Karandikar, Shashikant

    2012-04-01

    The past few years have seen a tremendous rise in the number of clinical trials conducted in India. This is been attributed to the huge patient population, genetic diversity, and rich technical pool in our country. However, the economical upsurge in the clinical trial industry has also caused concerns pertaining to the efficiency of the Regulatory Agencies and Ethics Committees (EC). The EC plays an important role in the regulation of clinical research at the local level. However, it is seen that many ECs are oblivious to their roles and responsibilities. It is reported that ECs lack standard operating procedures, do not have a proper composition or adequate representation, thus affecting their functions in regulating clinical research. Moreover, ECs seem to function in isolation, as self-sufficient bodies, having no communication with the regulatory agency or other ECs. This brings forth the need for ECs to come together and share their experiences and observations, with the aim of updating themselves and refining their functions. Efforts also need to be focused on capacity building, centralized registration of ECs, and bringing an oversight mechanism in place. The Ethics Committees in India need to work in close association with forums such as the Forum for Ethics Review Committees in India and the Forum for Ethical Review Committees in Asia Pacific, in an effort towards empowering themselves.

  6. Ethics committees in India: Facing the challenges!

    Directory of Open Access Journals (Sweden)

    Rashmi Kadam

    2012-01-01

    Full Text Available The past few years have seen a tremendous rise in the number of clinical trials conducted in India. This is been attributed to the huge patient population, genetic diversity, and rich technical pool in our country. However, the economical upsurge in the clinical trial industry has also caused concerns pertaining to the efficiency of the Regulatory Agencies and Ethics Committees (EC. The EC plays an important role in the regulation of clinical research at the local level. However, it is seen that many ECs are oblivious to their roles and responsibilities. It is reported that ECs lack standard operating procedures, do not have a proper composition or adequate representation, thus affecting their functions in regulating clinical research. Moreover, ECs seem to function in isolation, as self-sufficient bodies, having no communication with the regulatory agency or other ECs. This brings forth the need for ECs to come together and share their experiences and observations, with the aim of updating themselves and refining their functions. Efforts also need to be focused on capacity building, centralized registration of ECs, and bringing an oversight mechanism in place. The Ethics Committees in India need to work in close association with forums such as the Forum for Ethics Review Committees in India and the Forum for Ethical Review Committees in Asia Pacific, in an effort towards empowering themselves.

  7. Treatment Options for Wilms Tumor

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... come back) after it has been treated. Treatment Option Overview Key Points There are different types of ...

  8. Treatment Options for Myelodysplastic Syndromes

    Science.gov (United States)

    ... special light. Certain factors affect prognosis and treatment options. The prognosis (chance of recovery) and treatment options ... age and general health of the patient. Treatment Option Overview Key Points There are different types of ...

  9. Treatment Option Overview (Prostate Cancer)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  10. Treatment Option Overview (Myelodysplastic Syndromes)

    Science.gov (United States)

    ... special light. Certain factors affect prognosis and treatment options. The prognosis (chance of recovery) and treatment options ... age and general health of the patient. Treatment Option Overview Key Points There are different types of ...

  11. Treatment Option Overview (Esophageal Cancer)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  12. Treatment Option Overview (Childhood Rhabdomyosarcoma)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  13. Treatment Option Overview (Penile Cancer)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  14. Treatment Option Overview (Vulvar Cancer)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  15. Treatment Option Overview (Pancreatic Cancer)

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  16. Treatment Option Overview (Adrenocortical Carcinoma)

    Science.gov (United States)

    ... affect the prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  17. Treatment Options for Childhood Rhabdomyosarcoma

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  18. Treatment Options for Kaposi Sarcoma

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

  19. Treatment Options for Childhood Craniopharyngioma

    Science.gov (United States)

    ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... the brain where it was first found. Treatment Option Overview Key Points There are different types of ...

  20. 48 CFR 1403.101-70 - Technical evaluators and advisors.

    Science.gov (United States)

    2010-10-01

    ... GENERAL IMPROPER BUSINESS PRACTICES AND PERSONAL CONFLICTS OF INTEREST Safeguards 1403.101-70 Technical... committees, must render impartial, technically sound, and objective assistance and advice. (b) With the... a Conflict of Interest Certificate in a format approved by the HCA. If a potential COI exists, the...

  1. 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

  2. Technical challenges for dismantlement verification

    International Nuclear Information System (INIS)

    Olinger, C.T.; Stanbro, W.D.; Johnston, R.G.; Nakhleh, C.W.; Dreicer, J.S.

    1997-01-01

    In preparation for future nuclear arms reduction treaties, including any potential successor treaties to START I and II, the authors have been examining possible methods for bilateral warhead dismantlement verification. Warhead dismantlement verification raises significant challenges in the political, legal, and technical arenas. This discussion will focus on the technical issues raised by warhead arms controls. Technical complications arise from several sources. These will be discussed under the headings of warhead authentication, chain-of-custody, dismantlement verification, non-nuclear component tracking, component monitoring, and irreversibility. The authors will discuss possible technical options to address these challenges as applied to a generic dismantlement and disposition process, in the process identifying limitations and vulnerabilities. They expect that these considerations will play a large role in any future arms reduction effort and, therefore, should be addressed in a timely fashion

  3. Standing Concertation Committee

    CERN Document Server

    HR Department

    2009-01-01

    Main points examined at the meeting of 24 June 2009 Results of the 2009 MARS exercise The Committee took note of the results of the 2009 MARS exercise presented by the Head of the HR Department, expressing satisfaction for the early availability of the statistics and for the fact that the analysis of the results covered the last three years. Status report on the work on the five-yearly review The Committee took note of a presentation by P. Gildemyn on the data collection procedure for the 2010 five-yearly review (staff, fellows, associate members of the personnel, CHIS) and of the proposed work schedule. Implications for employment conditions of the discussions at the Finance Committee and Council on 17 and 18 June 2009 The Chairman briefly reported on the discussions at the meetings of the Finance Committee and Council in June 2009, on the 2010-2014 medium-term plan and the 2010 preliminary draft budget, as well as on the modified strategy and goals for 2009. The Committee ...

  4. 20 CFR 416.2035 - Optional supplementation: Additional State options.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Optional supplementation: Additional State options. 416.2035 Section 416.2035 Employees' Benefits SOCIAL SECURITY ADMINISTRATION SUPPLEMENTAL... § 416.2035 Optional supplementation: Additional State options. (a) Residency requirement. A State or...

  5. Novel preventive treatment options

    DEFF Research Database (Denmark)

    Longbottom, C; Ekstrand, K; Zero, D

    2009-01-01

    A number of novel preventive treatment options which, as with traditional methods, can be differentiated into 3 categories of prevention (primary, secondary and tertiary), have been and are being currently investigated. Those reviewed are either commercially available or appear relatively close...... of these techniques show considerable promise and dentists should be aware of these developments and follow their progress, the evidence for each of these novel preventive treatment options is currently insufficient to make widespread recommendations. Changes in dental practice should be explored to see how oral...

  6. Tank Space Options Report

    International Nuclear Information System (INIS)

    BOYLES, V.C.

    2001-01-01

    A risk-based priority for the retrieval of Hanford Site waste from the 149 single-shell tanks (SSTs) has been adopted as a result of changes to the Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1997) negotiated in 2000. Retrieval of the first three tanks in the retrieval sequence fills available capacity in the double-shell tanks (DSTs) by 2007. As a result, the HFFACO change established a milestone (M-45-12-TO1) requiring the determination of options that could increase waste storage capacity for single-shell tank waste retrieval. The information will be considered in future negotiations. This document fulfills the milestone requirement. This study presents options that were reviewed for the purpose of increasing waste storage capacity. Eight options are identified that have the potential for increasing capacity from 5 to 10 million gallons, thus allowing uninterrupted single-shell tank retrieval until the planned Waste Treatment Plant begins processing substantial volumes of waste from the double-shell tanks in 2009. The cost of implementing these options is estimated to range from less than $1 per gallon to more than $14 per gallon. Construction of new double-shell tanks is estimated to cost about $63 per gallon. Providing 5 to 10 million gallons of available double-shell tank space could enable early retrieval of 5 to 9 high-risk single-shell tanks beyond those identified for retrieval by 2007. These tanks are A-101, AX-101, AX-103, BY-102, C-107, S-105, S-106, S-108, and S-109 (Garfield et al. 2000). This represents a potential to retrieve approximately 14 million total curies, including 3,200 curies of long-lived mobile radionuclides. The results of the study reflect qualitative analyses conducted to identify promising options. The estimated costs are rough-order-of magnitude and, therefore, subject to change. Implementing some of the options would represent a departure from the current baseline and may adversely impact the

  7. Thermal test options

    International Nuclear Information System (INIS)

    Koski, J.A.; Keltner, N.R.; Sobolik, K.B.

    1993-02-01

    Shipping containers for radioactive materials must be qualified to meet a thermal accident environment specified in regulations, such at Title 10, Code of Federal Regulations, Part 71. Aimed primarily at the shipping container design, this report discusses the thermal testing options available for meeting the regulatory requirements, and states the advantages and disadvantages of each approach. The principal options considered are testing with radiant heat, furnaces, and open pool fires. The report also identifies some of the facilities available and current contacts. Finally, the report makes some recommendations on the appropriate use of these different testing methods

  8. Lighting Options for Homes.

    Energy Technology Data Exchange (ETDEWEB)

    Baker, W.S.

    1991-04-01

    This report covers many aspects of various lighting options for homes. Types of light sources described include natural light, artificial light, incandescent lamps, fluorescent lamps, and high intensity discharge lamps. A light source selection guide gives the physical characteristics of these, design considerations, and common applications. Color, strategies for efficient lighting, and types of lighting are discussed. There is one section giving tips for various situations in specific rooms. Rooms and types of fixtures are shown on a matrix with watts saved by using the recommended type lighting for that room and room location. A major emphasis of this report is saving energy by utilizing the most suitable, recommended lighting option. (BN)

  9. 75 FR 27614 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2010-05-17

    ... Environment Protection Committee. --Consideration of the report of the Maritime Safety Committee... Session of the International Maritime Organization (IMO) Council to be held at the IMO headquarters in... HNS Convention. --World Maritime University: --IMO International Maritime Law Institute: --Protection...

  10. 77 FR 76164 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-12-26

    ... atmospheric pollution --Development of international measures for minimizing the transfer of invasive aquatic... pollution hazards of chemicals and preparation of consequential amendments --Additional guidelines for... DEPARTMENT OF STATE [Public Notice 8133] Shipping Coordinating Committee; Notice of Committee...

  11. Strategic growth options

    NARCIS (Netherlands)

    Kulatilaka, N.; Perotti, E.C.

    1998-01-01

    We provide a strategic rationale for growth options under uncertainty and imperfect corn-petition. In a market with strategic competition, investment confers a greater capability to take advantage of future growth opportunities. This strategic advantage leads to the capture of a greater share of the

  12. New Options, Old Concerns.

    Science.gov (United States)

    O'Neil, John

    1996-01-01

    Will greater school choice result in more responsive, higher quality schools and happier parents? Or will proliferating options further sort students and families by race, social class, and special interest? Increasingly, education is viewed as a private good. If parents become autonomous, self-interested consumers, erosion of common purposes and…

  13. Heterogeneity and option pricing

    NARCIS (Netherlands)

    Benninga, Simon; Mayshar, Joram

    2000-01-01

    An economy with agents having constant yet heterogeneous degrees of relative risk aversion prices assets as though there were a single decreasing relative risk aversion pricing representative agent. The pricing kernel has fat tails and option prices do not conform to the Black-Scholes formula.

  14. Option Pricing and Momentum

    NARCIS (Netherlands)

    Rodriguez, J.C.

    2007-01-01

    If managers are reluctant to fully adjust dividends to changes in earnings, stock returns and changes in the dividend yield will tend to be negatively correlated. When this is the case, stock returns will exhibit positive autocorrelation, or mo- mentum. This paper studies the pricing of options in

  15. Idaho's Energy Options

    Energy Technology Data Exchange (ETDEWEB)

    Robert M. Neilson

    2006-03-01

    This report, developed by the Idaho National Laboratory, is provided as an introduction to and an update of the status of technologies for the generation and use of energy. Its purpose is to provide information useful for identifying and evaluating Idaho’s energy options, and for developing and implementing Idaho’s energy direction and policies.

  16. 75 FR 43156 - Federal Advisory Committee; Missile Defense Advisory Committee

    Science.gov (United States)

    2010-07-23

    ... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Missile Defense Advisory Committee AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of closed meeting. SUMMARY: Under the... Defense announces that the Missile Defense Advisory Committee will meet on August 4 and 5, 2010, in...

  17. Nuclear utility self-assessment as viewed by the corporate nuclear safety committee

    International Nuclear Information System (INIS)

    Corcoran, W.R.

    1992-01-01

    This paper discusses how corporate nuclear safety committees use the principles of self-assessment to enhance nuclear power plant safety performance. Corporate nuclear safety committees function to advise the senior nuclear power executive on matters affecting nuclear safety. These committees are required by the administrative controls section of the plant technical specifications which are part of the final safety analysis report and the operating license. Committee membership includes senior utility executives, executives from sister utilities, utility senior technical experts, and outside consultants. Current corporate nuclear safety committees often have a finely tuned intuitive feel for self-assessment that they use to probe the underlying opportunities for quality and safety enhancements. The questions prompted by the self-assessment orientation enable the utility line organization members to gain better perspectives on the characteristics of the organizational systems that they manage and work in

  18. Expert Committee on College Libraries

    OpenAIRE

    Joy, V. P.; Raman Nair, R.; Ayub, M.

    1994-01-01

    Importance of library and information services in higher education was emphasized in India by many committees of Government of India from 1917 including Calcutta University Commission under Sir Michael Saddler, University Education Commission (1949) chaired by Dr. S. Radhakrishnan, Ranganathan Committee (1958), Education Commission (1966) chaired by D.S. Kothari, as well as Sen Committee, Mehrotra Committee etc of UGC. But as education being a State subject; union government could not go beyo...

  19. SENIOR STAFF ADVANCEMENT COMMITTEE (SSAC)

    CERN Document Server

    2000-01-01

    Composition and mandateThe Senior Staff Advancement Committee is composed of members nominated ad persona by the Director-General.The Committee examines proposals from Divisions concerning promotions to grade 13 in Career Path IX, changes of career path to Career Path IX and advancements to the exceptional grade in Career path VIII.The Director-General may consult the Committee on any matter related to senior staff careers.The Committee makes its recommendations to the Director-General.

  20. Plasma Science Committee (PLSC)

    International Nuclear Information System (INIS)

    1990-01-01

    The Plasma Science Committee (PLSC) is a standing committee under the auspices of the Board on Physics and Astronomy, Commission on Physical Sciences, Mathematics, and Applications of the National Academy of Sciences--National Research Council. Plasma sciences represent a broad and diverse field. The PLSC has accepted the responsibility of monitoring the continuing development and assessing the general health of the field as whole. Although select advisory bodies have been created to address specific issues that affect plasma science, such as the Fusion Policy Advisory Committee (FPAC), the PLSC provides a focus for the plasma science community that is unique and essential. The membership of the PLSC is drawn from research laboratories in universities, industry, and government. Areas of expertise on the committee include accelerators and beams, space physics, astrophysics, computational physics and applied mathematics, fusion plasmas, fundamental experiments and theory, radiation sources, low temperature plasmas, and plasma-surface interactions. The PLSC is well prepared to respond to requests for studies on specific issues. This report discusses ion of the PLSC work