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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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…

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…

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...

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...

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...

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...

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...

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

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...

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

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…

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

Institute of Scientific and Technical Information of China (English)

无

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.

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

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.

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)

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.)

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)

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...

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

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

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...

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

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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

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.

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...

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...

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.

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)

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...

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...

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

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

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

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

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...

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

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)

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…

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

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...

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.

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

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...

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

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

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...

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.

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

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

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

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.

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…

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.

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

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...

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...

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

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...

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.

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...

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.

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

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.

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

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.

[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.

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.

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

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

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.

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

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.

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)

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

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...

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...

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...

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...

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.

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...

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

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.

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...

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.

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

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...

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.

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).

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.

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.

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

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

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

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.

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

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).

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

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.

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

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.

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)

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.

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

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…

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....

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...

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.

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.

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

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.

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.)

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...

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.

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 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...

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

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.

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.

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

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

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

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

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.

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

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

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

International Nuclear Information System (INIS)

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

1986-01-01

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

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...

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...

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...

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...

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...

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

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.

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

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

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.

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...

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)

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)

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

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)

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)

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...

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...

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...

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

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

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.

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

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

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

The Technical Student Programme draws Norwegians

CERN Multimedia

2005-01-01

Erik Hejne, second from left, Chairman of the Technical Students Committee, and Jens Vigen, who is concerned spefically with Norwegian students at CERN, with some of the Norwegian technical students who arrived at CERN in spring 2005, together with their teachers. From mid-April, CERN's PH and IT Departments are hosting ten Norwegian students from Bergen University College, the Sør-Trøndelag University College and the University of Science and Technology in Trondheim to take part in the Laboratory's Technical Student Programme. The Technical Student Programme is open to students of universities and technical higher education establishments in the Member States who, in the course of their studies, are required to complete a period of professional training in industry or in a laboratory. Around 70 Technical Students come to work at CERN each year. Selected by a committee, they spend between six months and one year with the Organization. The programme is funded by CERN. However, once the Laboratory's quota of...

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.

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

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.

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

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...

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

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.

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

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...

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

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

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

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.

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

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.)

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

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.)

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.

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

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

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.)

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

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.

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

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

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...

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...

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

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

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

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).

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;

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.

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

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

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

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

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Kim, Young Min

1998-12-01

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

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

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

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

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).

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

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.

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 ...

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

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...

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

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…

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons

International Nuclear Information System (INIS)

Omberg, R.P.; Walter, C.E.

1993-01-01

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the ''Fission Options'' provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium

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

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

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

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.;

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)

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

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

Do committees ru(i)n the bio-political culture? On the democratic legitimacy of bioethics committees.

Science.gov (United States)

Friele, Minou Bernadette

2003-08-01

Bioethical and bio-political questions are increasingly tackled by committees, councils, and other advisory boards that work on different and often interrelated levels. Research ethics committees work on an institutional or clinical level; local advisory boards deal with biomedical topics on the level of particular political regions; national and international political advisory boards try to answer questions about morally problematic political decisions in medical research and practice. In accordance with the increasing number and importance of committees, the quality of their work and their functional status are being subjected to more and more scrutiny. Besides overall criticism regarding the quality of their work, particular committees giving political advice are often suspected of being incompatible with democratic values, such as respect for affected parties, representation of diverse values and transparency in the decision-making processes. Based on the example of the German National Ethics Council, whose inauguration caused a still ongoing debate on the aims and scopes of committees in general, this paper discusses: (1) the requirements of modern democratic societies in dealing with complex scientific-technical problems; (2) the composition and organisation of committees working as political advisory boards; and (3) the appointment procedures and roles of laymen and experts, and here in particular of ethicists, who may legitimately be taken on by a committee. I will argue that bioethics committees do not necessarily endanger democratic values, but can considerably improve their realisation in democratic decision-making procedures--if, and only if, they do not act as substitutes for parliamentarian processes, but help prepare parliamentarian processes to be organised as rationally as possible.

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

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 ...

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...

Wind turbine certification - the committee draft by IEC-TC88-WG9

Energy Technology Data Exchange (ETDEWEB)

Hauge Madsen, P [Risoe National Lab., Wind Energy and Atmospheric Physics Dept., Roskilde (Denmark)

1999-03-01

In 1995 the Technical Committee TC88 of the International Electrotechnical Commission decided to start a new work item, namely to prepare a standard for the certification procedures for wind turbines with respect to safety, performance, interaction with the public grid, environmental requirements and the documentation requested by the certification bodies. The purpose was to provide a common basis for certification of wind turbines, including a basis for accreditation of certification bodies and mutual recognition of certificates. A working group (WG9) was created to prepare a committee draft. WG9 submitted the result late in 1998 to TC88. This paper presents the committee draft Standard, which defines a certification system for Wind Turbine Generator Systems. Key issues in the evaluation of conformity with these standards and identified needs for other technical criteria and procedures are presented. (au) 10 refs.

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)

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)

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.

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.

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

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

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.)

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)

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)

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

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...

An informal judgment assessment of subsidence mitigation options for low-level radioactive waste management on the Nevada Test Site

International Nuclear Information System (INIS)

Crowe, B.M.; Besinger, H.; Dolenc, M.

1999-01-01

An assessment of options to mitigate the effects of subsidence at low-level radioactive waste disposal sites on the Nevada Test Site was conducted using an informal method of expert judgment. Mitigation options for existing waste cells and future waste cells were identified by a committee composed of knowledgeable personnel from the DOE and DOE-contractors. Eight ranking factors were developed to assess the mitigation options and these factors were scored through elicitation of consensus views from the committee. Different subsets of the factors were applied respectively, to existing waste cells and future waste cells, and the resulting scores were ranked using weighted and unweighted scores. These scores show that there is a large number of viable mitigation options and considerable flexibility in assessing the subsidence issue with a greater range of options for future waste cells compared to existing waste cells. A highly ranked option for both existing and future waste cells is covering the waste cells with a thick closure cap of native alluvium

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...

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.

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

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...

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

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.

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

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

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

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. .

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.

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...

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

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

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.

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.

INEL Operable Unit 7-13 containment and stabilization configuration option

International Nuclear Information System (INIS)

Raivo, B.D.; Richardson, J.G.; Nickelson, D.F.

1993-05-01

A containment and stabilization configuration option has been developed for the Idaho National Engineering Laboratory's Subsurface Disposal Area Operable Unit 7-13, the transuranic (TRU)-contaminated waste pits and trenches. The configuration option is presented as an end-to-end system block diagram. Functional subelements are separately discussed, and technical background information, assumptions, input, high-level subelement requirements, and output are presented for each option

Human Participants in Engineering Research: Notes from a Fledgling Ethics Committee.

Science.gov (United States)

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

2015-08-01

For the past half-century, issues relating to the ethical conduct of human research have focused largely on the domain of medical, and more recently social-psychological research. The modern regime of applied ethics, emerging as it has from the Nuremberg trials and certain other historical antecedents, applies the key principles of: autonomy, respect for persons, beneficence, non-maleficence, and justice to human beings who enter trials of experimental drugs and devices (Martensen in J Hist Med Allied Sci 56(2):168-175, 2001). Institutions such as Institutional Review Boards (in the U.S.) and Ethics Committees (in Europe and elsewhere) oversee most governmentally-funded medical research around the world, in more than a hundred nations that are signers of the Declaration of Helsinki (World Medical Association 2008). Increasingly, research outside of medicine has been recognized to pose potential risks to human subjects of experiments. Ethics committees now operate in the US, Canada, the U.K. and Australia to oversee all governmental-funded research, and in other jurisdictions, the range of research covered by such committees is expanding. Social science, anthropology, and other fields are falling under more clear directives to conduct a formal ethical review for basic research involving human participants (Federman et al. in Responsible research: a systems approach to protecting research participants. National Academies Press, Washington, 2003, p. 36). The legal and institutional response for protecting human subjects in the course of developing non-medical technologies, engineering, and design is currently vague, but some universities are establishing ethics committees to oversee their human subjects research even where the experiments involved are non-medical and not technically covered by the Declaration of Helsinki. In The Netherlands, as in most of Europe, Asia, Latin America, or Africa, no laws mandate an ethical review of non-medical research. Yet, nearly 2

Final Technical Report: Hydrogen Codes and Standards Outreach

Energy Technology Data Exchange (ETDEWEB)

Hall, Karen I.

2007-05-12

This project contributed significantly to the development of new codes and standards, both domestically and internationally. The NHA collaborated with codes and standards development organizations to identify technical areas of expertise that would be required to produce the codes and standards that industry and DOE felt were required to facilitate commercialization of hydrogen and fuel cell technologies and infrastructure. NHA staff participated directly in technical committees and working groups where issues could be discussed with the appropriate industry groups. In other cases, the NHA recommended specific industry experts to serve on technical committees and working groups where the need for this specific industry expertise would be on-going, and where this approach was likely to contribute to timely completion of the effort. The project also facilitated dialog between codes and standards development organizations, hydrogen and fuel cell experts, the government and national labs, researchers, code officials, industry associations, as well as the public regarding the timeframes for needed codes and standards, industry consensus on technical issues, procedures for implementing changes, and general principles of hydrogen safety. The project facilitated hands-on learning, as participants in several NHA workshops and technical meetings were able to experience hydrogen vehicles, witness hydrogen refueling demonstrations, see metal hydride storage cartridges in operation, and view other hydrogen energy products.

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

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

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.

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.)

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

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...

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

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

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.

2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY

Energy Technology Data Exchange (ETDEWEB)

Seitz, R.

2011-12-30

The Performance Assessment Community of Practice (PA CoP) was developed in 2008 to improve consistency and quality in the preparation of performance assessments (PAs) and risk assessments across the Department of Energy (DOE) Complex. The term, PA, is used to represent all of these modeling applications in this report. The PA CoP goals are to foster the exchange of information among PA practitioners and to share lessons learned from PAs conducted for DOE, commercial disposal facilities, and international entities. Technical exchanges and workshops are a cornerstone of PA CoP activities. Previous technical exchanges have addressed Engineered Barriers (2009 - http://www.cresp.org/education/workshops/pacop/), the Advanced Simulation Capability for Environmental Management and the Cementitious Barriers Partnership (2010 - http://srnl.doe.gov/copexchange/links.htm). Each technical exchange also includes summary presentations regarding activities at DOE, the Nuclear Regulatory Commission (NRC) and other organizations (e.g., International Atomic Energy Agency (IAEA)) as well as a number of presentations from selected sites to provide insight and perspective from on-going modeling activities. Through the deployment of PA Assistance Teams, the PA CoP has also been engaged in the development of new PAs across the DOE Complex. As a way of improving consistency in the preparation of new PAs, the teams provide technical advice and share experiences, noteworthy practices, and lessons learned from previous Low-Level Waste Disposal Facility Federal Review Group (LFRG) reviews. Teams have provided support for PAs at Hanford, Idaho, Paducah and Portsmouth. The third annual PA CoP Technical Exchange was held on May 25-26, 2011 in Atlanta, GA. The PA CoP Steering Committee Meeting held its first meeting on May 24 prior to the Technical Exchange. Decision making using models and software quality assurance were the topical emphasis for the exchange. A new feature at the 2011 technical

Recent developments in spent fuel management in Norway - 59260

International Nuclear Information System (INIS)

Bennett, Peter J.; Oberlaender, Barbara C.

2012-01-01

Spent Nuclear Fuel (SNF) in Norway has arisen from irradiation of fuel in the NORA, Jeep I and Jeep II reactors at Kjeller, and in the Heavy Boiling Water Reactor (HBWR) in Halden. In total there is some 16 tonnes of SNF, with 12 tons of aluminium-clad fuel, of which 10 tonnes is metallic uranium fuel and the remainder oxide (UO 2 ). The portion of this fuel that is similar to commercial fuel (UO 2 clad in Zircaloy) may be suitable for direct disposal on the Swedish model or in other repository designs. However, metallic uranium and/or fuels clad in aluminium are chemically reactive and there would be risks associated with direct disposal. Two committees were established by the Government of Norway in January 2009 to make recommendations for the interim storage and final disposal of spent fuel in Norway. The Technical Committee on Storage and Disposal of Metallic Uranium Fuel and Al-clad Fuels was formed with the mandate to recommend treatment (i.e. conditioning) options for metallic uranium fuel and aluminium-clad fuel to render them stable for long term storage and disposal. This committee, whose members were drawn from the nuclear industry, reported in January 2010, and recommended commercial reprocessing as the best option for these fuels. The Phase-2 committee, which in part based its work on the work of previous committees and on the report of the Technical Committee, had the mandate to find the most suitable technical solution and localisation for intermediate storage for spent nuclear fuel and long-lived waste. The membership of this committee was chosen to represent a broad cross section of stakeholders. The committee evaluated different solutions and their associated costs, and recommended one of the options. The committee's report published in early 2011. This paper summarises the conclusions of the two committees, and thereby illustrates the steps taken by one country to formulate a strategy for the long-term management of its SNF. (authors)

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

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

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

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.

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

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...

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

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.

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.

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.

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

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...

Status and strategy for technical cooperation between Korea and nuclear advanced countries

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Noh, In Young

1998-12-01

As part of its efforts to promote peaceful used of nuclear energy as well as achieve self-reliance in nuclear technology on a national level, 7 nuclear joint coordination committees and consultation meeting are in operation. These committees include. The R.O.K./U.K. Nuclear Energy Consultation Meeting, the Korea-France Joint Coordination Committee, the Korea-Russia coordination committee and the Korea/Australia nuclear policy consultation. As a means not only to enhance the status of Korea in the international community, but also to effectively and positively cope with rapidly changing international nuclear developments, the current status of nuclear power programs in nuclear advanced countries, including United Kingdom, France and Russia and of technical cooperation with Australia, were covered in this report. This report can be also help in setting up our position and discussion plans for each item to be discussed in bilateral cooperation meetings through an understanding background and results of technical cooperation implemented so far with KAERI and reviewing the agreed items. (author). 9 tabs., 6 figs

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

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

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

78 FR 25447 - Establishment of the Discretionary Advisory Committee on Heritable Disorders in Newborns and...

Science.gov (United States)

2013-05-01

... Health Service Act (PHS), 42 U.S.C. 217a: Advisory councils or committees as well as provisions of Public... newborn and childhood screening and technical information for the development of policies and priorities... Administration--or their designees. The Chair and other members are (a) medical, technical, public health or...

Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes; Debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-09-15

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

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

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

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).

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...

78 FR 77181 - Self-Regulatory Organizations; The Options Clearing Corporation; Advance Notice Concerning the...

Science.gov (United States)

2013-12-20

... financial system because it will enhance the transparency of OCC's governance arrangements. The advance...-Regulatory Organizations; The Options Clearing Corporation; Advance Notice Concerning the Governance... Advance Notice This advance notice concerns the charter of the Governance Committee (``GC Charter'') of...

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.

Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2005-09-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

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.

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.

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

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

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

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.

Comparative studies of energy supply options in Poland for 1997-2020

International Nuclear Information System (INIS)

2002-08-01

Poland depends heavily on coal to satisfy national demands for electricity. Currently, over 90% of electricity generation is produced by coal fired power plants. Because of the large dependence on coal and environmental impacts of large-scale coal combustion the country looks for a more diversified energy mix. As ways of diversification, Poland is considering the expanded role of natural gas and, potentially, nuclear power in the future energy mix. This publication describes the analysis of several diversification options for the Polish energy sector conducted by a national team in the framework of an IAEA Technical Cooperation project implemented in 1999-2000. The project provided a set of proven IAEA methodologies and tools that was utilized for a comprehensive analysis and comparison of the options including their economic competitiveness and environmental impacts. The publication is intended primarily for senior experts and technical staff in governmental organizations, research institutes, industries and utilities, who are in charge of technical analysis or decision making related to long term energy and power supply options. The report was prepared in 2001 by the staff of the Energy Market Agency (EMA, Warsaw, Poland) that was the leading Polish organization in carrying out the study

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1991-12-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. This document, Volume 1, identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues

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

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.

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-01-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. Volume 1 identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues. This document Volume 2 and Volume 3 discusses each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTs, respectively

Proposal for the Award of Two Contracts for the Technical Services for Work on Components of CERN Particle Accelerators and High Energy Physics Experiments

CERN Document Server

2003-01-01

This document concerns the award of two contracts for the technical services for work on components of CERN particle accelerators and high energy physics experiments. Following a market survey carried out among 73 firms in fourteen Member States, a call for tenders (IT-3156/SPL) was sent on 4 November 2002 to three consortia in four Member States. By the closing date, CERN had received tenders from the three consortia. The Finance Committee is invited to agree to the negotiation of two contracts with: 1) the consortium SERCO FACILITIES MANAGEMENT (NL) - GERARD PERRIER INDUSTRIE (FR) - INEO ALPES (FR), the lowest bidder, for approximately 55% of the technical services for work on components of CERN particle accelerators and high energy physics experiments, for an initial period of five years and for a total amount not exceeding 37 435 270 euros (54 902 500 Swiss francs), subject to revision for inflation from 1 January 2005. The contract will include options for two one-year extensions beyond the initial five-...

Addendum to Technical Proposal: A Facility to Search for Hidden Particles (SHiP) at the CERN SPS

CERN Document Server

SHiP Collaboration

2015-01-01

With the Technical Proposal submitted to the SPSC committee in April 2015, the SHiP collaboration declared its interest in proceeding towards a Comprehensive Design Study phase with the aim of preparing for the Technical Design Reports pending an approval by the CERN committees. Following the recommendation by the SPSC, it has been decided to complement the TP with this addendum that provides an update of the key aspects for the review of the SHiP project.

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...

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

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.

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

New Brunswick Market Design Committee : First interim report

International Nuclear Information System (INIS)

2001-10-01

In June 2001, a Market Design Committee was appointed by the Government of New Brunswick tp provide some advice on the best ways to implement the electricity restructuring initiatives detailed in a White Paper on energy policy in New Brunswick. The Market Design Committee is a very technical committee that was set up with a number of goals in mind: make recommendations concerning all codes and operating protocols, make recommendations on market surveillance and the establishment of a workable competitive market, take into account the reliability of supply for New Brunswick, address ways by which to avoid rate shock to existing self-generators, make recommendations for mitigation of market power in the wholesale and large retail markets, evaluate methods of stranded cost recovery, make recommendations on the requirement for reciprocity in New Brunswick electricity market design, and review the role and treatment of small-scale, on-site electricity generation and make recommendations. The final recommendations are set to be presented in April 2002. This document details the progress realized to date and outlines the plans made for the subsequent phases of the work. The different topics discussed in this document each form the basis for one section of the report. They are: market design committee constitution and process, basic market model, market power issues, transmission issues, environment and renewables, and next steps for the market design committee

76 FR 70778 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Science.gov (United States)

2011-11-15

... Regarding Concentration Averaging and Encapsulation of Low-Level Radioactive Waste (Open)--The Committee... Branch Technical Position on Concentration Averaging and Encapsulation of Low-Level Radioactive Waste. 1... Hitachi Nuclear Energy Licensing Topical Report NEPC-33173P-A, Supplement 2, Parts 1, 2, and 3, ``Analysis...

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.

Stock and option portfolio using fuzzy logic approach

Science.gov (United States)

Sumarti, Novriana; Wahyudi, Nanang

2014-03-01

Fuzzy Logic in decision-making process has been widely implemented in various problems in industries. It is the theory of imprecision and uncertainty that was not based on probability theory. Fuzzy Logic adds values of degree between absolute true and absolute false. It starts with and builds on a set of human language rules supplied by the user. The fuzzy systems convert these rules to their mathematical equivalents. This could simplify the job of the system designer and the computer, and results in much more accurate representations of the way systems behave in the real world. In this paper we examine the decision making process of stock and option trading by the usage of MACD (Moving Average Convergence Divergence) technical analysis and Option Pricing with Fuzzy Logic approach. MACD technical analysis is for the prediction of the trends of underlying stock prices, such as bearish (going downward), bullish (going upward), and sideways. By using Fuzzy C-Means technique and Mamdani Fuzzy Inference System, we define the decision output where the value of MACD is high then decision is "Strong Sell", and the value of MACD is Low then the decision is "Strong Buy". We also implement the fuzzification of the Black-Scholes option-pricing formula. The stock and options methods are implemented on a portfolio of one stock and its options. Even though the values of input data, such as interest rates, stock price and its volatility, cannot be obtain accurately, these fuzzy methods can give a belief degree of the calculated the Black-Scholes formula so we can make the decision on option trading. The results show the good capability of the methods in the prediction of stock price trends. The performance of the simulated portfolio for a particular period of time also shows good return.

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.

Disposal options for disused radioactive sources

International Nuclear Information System (INIS)

2005-01-01

This report presents a review of relevant information on the various technical factors and issues, as well as approaches and relevant technologies, leading to the identification of potential disposal options for disused radioactive sources. The report attempts to provide a logical 'road map' for the disposal of disused radioactive sources, taking into consideration the high degree of variability in the radiological properties of such types of radioactive waste. The use of borehole or shaft type repositories is highlighted as a potential disposal option, particularly for those countries that have limited resources and are looking for a simple, safe and cost effective solution for the disposal of their radioactive source inventories. It offers information about usage and characteristics of radioactive sources, disposal considerations, identification and screening of disposal options as well as waste packaging and acceptance criteria for disposal. The information provided in the report could be adapted or adopted to identify and develop specific disposal options suitable for the type and inventory of radioactive sources kept in storage in a given Member State

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

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)

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...

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.

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.

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...

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Krisman, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-07-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the acid pit and transuranic pits and trenches (TRU-PTs) at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues lated with ISV application at the SDA. The activities of the ISV Steering Committee are summarized in a three-volume report. Volume I identifies the systematic approach used to identify and prioritize the ISV technical issues and briefly discusses the methodology that will be employed to resolve these issues. Volumes 2 and 3 discuss each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTS, respectively. The three-volume report is a working document that will be updated as necessary to reflect current evaluation strategy for the ISV technology. This is Volume 3

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

Management options for food production systems affected by a nuclear accident. Task 2 options for minimising the production of contaminated milk

CERN Document Server

Smith, J G; Mercer, J A; Nisbet, A F; Wilkins, B T

2002-01-01

This report describes an evaluation of three possible means by which the production of waste milk could be reduced following a nuclear accident. The three options studied are the reduction of contaminated pasture in the diet, the drying off of lactating dairy cattle and the slaughter of dairy cattle. The practicability of each of these is considered using criteria such as technical feasibility, capacity, cost, impact and acceptability, where appropriate. In theory reductions in waste milk arisings can be achieved with each option, however, there are a number of limitations associated with their practical application.

75 FR 25855 - Clean Air Act Advisory Committee (CAAAC): Notice of Meeting

Science.gov (United States)

2010-05-10

...) Permits/NSR/Toxics Integration--Liz Naess, (919) 541-1892; (2) Economic Incentives and Regulatory... Air Act of 1990. The Committee advises on economic, environmental, technical scientific, and...., Washington, DC. Seating will be available on a first come, first served basis. The Economic Incentives and...

Portability of Technical Skills Across Occupations

OpenAIRE

Mukuni, Joseph Siloka

2012-01-01

In the literature, much has been reported about skill shortages in the labor market and many solutions have been suggested but most of them do not appear to work well for developing countries. This study investigated the place of portable technical skills as an option for addressing skill shortages, particularly in developing countries. The objective of the study was to determine whether different occupations have portable technical skills, which graduates of workforce development programs ca...

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

Position adopted by the government about the safety options of the EPR reactor project; Prise de position du gouvernement concernant les options de surete du projet de reacteur EPR

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-10-01

On September 28, 2004, on behalf of the French ministers in charge of nuclear safety, the general director of nuclear safety and radiation protection addressed to the president of Electricite de France (EdF) a letter presenting the government's position about the safety options of the EPR (European Pressurized Reactor) project. On the basis of the examination carried out by the nuclear safety authority (ASN) and by the permanent group of reactor experts, the government has considered these options as satisfactory with respect to the safety improvement objectives. Therefore, the government requested EdF to comply with these technical rules for any future reactor development. This dossier includes: the letter of the government, the technical directives for the design and construction of the next generation of PWR-type reactors, the technical rules relative to the design of the main primary and secondary coolant circuits of PWR-type reactors, and the technical file about the safety of the EPR project reprinted from the 2003 report of nuclear safety and radiation protection authority. (J.S.)

Greenhouse gas abatement in Senegal. A case study of least-cost options

International Nuclear Information System (INIS)

Amous, S.; Revet, D.; Sokona, Y.

1994-01-01

The first stage of the study was to make a preliminary inventory of greenhouse gas (GHG) emissions for the base year 1988. Following this seven no regret technical options for emission reduction were investigated and the costs calculated, allowing the identification of three least-cost options. The three least-cost options must be implemented first because of their negative costs. The economic benefits of both abatement scenarios are characterized by a negative global cost whatever the discount rate is. (author)

Committee for International Conference on Mechanical Engineering Research (ICMER 2011)

Science.gov (United States)

Yusoff, Ahmad Razlan Bin

2012-09-01

Scientific Advisory Committee: 1) Prof. Dr. Ahmad Kamal Ariffin (UKM) 2) Prof. Dr. Hj. Rosli Abu Bakar (UMP) 3) Prof. Dr. Hanafi Ismail (USM) 4) Prof. Ir. Dr. Mohd Jailani Mohd Nor (MoHE) 5) Prof. Dr. Zahari Taha (UMP) 6) Prof. Dr. Masjuki Haji Hassan 7) Prof. Ir. Dr. Ramesh Singh (UNITEN) 8) Prof. Dr. Razali Ayob (UTEM) 9) Prof. Dr. Wan Khairuddin (UTM) 10) Prof. Dr. Sulaiman Hj. Hasan (UTHM) 11) Prof. Dr. Zuraidah Mohd. Zain (UniMAP) 12) Prof. Dr. Horizon Gitano (USM) 13) Prof. Dr. K.V Sharma (UMP) 14) Prof. Dr. Shahrani Anuar (UMP) 15) Assoc. Prof. Dr. Abd Rashid Abd. Aziz (UTP) 16) Assoc. Prof. Dr. Aidy Ali (UPM) 17) Assoc. Prof. Dr. Saidur Rahman (UM) 18) Assoc. Prof. Dr. Md Abdul Maleque (UIA) Organizing Committee Chairman: Prof. Dr. Hj. Rosli Abu Bakar Co-Chair: Prof. Dr. Zahari Taha Co-Chair: Prof. Ir. Dr. Jailani Salihon Secretary: Dr. Rizalman Mamat Committee on Keynote Speaker 1) Kumaran Kadirgama (Chair) 2) Prof. Dr. K.V. Sharma 3) Haji Amirruddin Abdul Kadir 4) Miminorazeansuhaila Loman 5) Mohd Akramin Mohd Romlay Technical Committee (Peer Review & Proceedings) 1) Dr. Abdul Adam Abdullah (Chair) 2) Dr. Ahmad Razlan Yusoff 3) Mohd Yusof Taib 4) Dr. Md. Mustafizur Rahman 5) Dr. Hjh. Yusnita Rahayu 6) Dr. Gigih Priyandoko 7) Dr. Agung Sudrajad 8) Muhammad Hatifi Mansor 9) Mohd Fadzil Abdul Rahim Technical Committee (Panels & Session Chairs) 1) Dr. Mahadzir Ishak (Chair) 2) Prof. Dr. Shahrani Anuar 3) Dr. Maisara Mohyeldin Gasim Mohamed 4) Muhammad Ammar Nik Mu'tasim 5) Ahmad Basirul Subha bin Alias Technical Committee (Journal Publication) 1) Dr. Ahmad Razlan bin Yusoff (Chair) 2) Mohd Yusof Taib 3) Dr. Mahadzir Ishak 4) Dr. Abdul Adam Abdullah 5) Hj. Amirruddin Abdul Kadir 6) Hadi Abdul Salaam Bureau of Publicity & Website 1) Dr. Muhamad Arifpin Mansor (Chair) 2) Amir Abdul Razak 3) Idris Mat Sahat 4) Prof. Dr. Hj. Rosli Abu Bakar 5) Muhamad Zuhairi Sulaiman 6) Dr. Sugeng Ariyono 7) Asnul Hadi Ahmad 8) Mohd Tarmizy Che Kar 9) Mohd Padzly Radzi Bureau of

Technical opportunities to reduce global anthropogenic emissions of nitrous oxide

Science.gov (United States)

Winiwarter, Wilfried; Höglund-Isaksson, Lena; Klimont, Zbigniew; Schöpp, Wolfgang; Amann, Markus

2018-01-01

We describe a consistent framework developed to quantify current and future anthropogenic emissions of nitrous oxide and the available technical abatement options by source sector for 172 regions globally. About 65% of the current emissions derive from agricultural soils, 8% from waste, and 4% from the chemical industry. Low-cost abatement options are available in industry, wastewater, and agriculture, where they are limited to large industrial farms. We estimate that by 2030, emissions can be reduced by about 6% ±2% applying abatement options at a cost lower than 10 €/t CO2-eq. The largest abatement potential at higher marginal costs is available from agricultural soils, employing precision fertilizer application technology as well as chemical treatment of fertilizers to suppress conversion processes in soil (nitrification inhibitors). At marginal costs of up to 100 €/t CO2-eq, about 18% ±6% of baseline emissions can be removed and when considering all available options, the global abatement potential increases to about 26% ±9%. Due to expected future increase in activities driving nitrous oxide emissions, the limited technical abatement potential available means that even at full implementation of reduction measures by 2030, global emissions can be at most stabilized at the pre-2010 level. In order to achieve deeper reductions in emissions, considerable technological development will be required as well as non-technical options like adjusting human diets towards moderate animal protein consumption.

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...

Dismantling of civilian nuclear powered fleet technical support vessels. engineering solutions - 59386

International Nuclear Information System (INIS)

Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

2012-01-01

At the present time six nuclear technical support vessels are operated and maintained by Atomflot. Two of them (Volodarsky FTB (floating technical base) and Lepse FTB) were taken out of service for decommissioning and are stored afloat. One more vessel Lotta FTB should be decommissioned during next two years. The nuclear technological support ships carrying spent nuclear fuel (SNF), liquid and solid radioactive wastes (LRW and SRW) appear to be a possible radiation contamination of Murmansk region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull's structures technical condition. As a result of this in the context of the Federal Program 'Nuclear and Radiation Safety' (2008-2015) NIPTB Onega OAO was engaged by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB. Before developing of nuclear technological support ships decommissioning projects the technical and economic assessment of decommissioning/dismantling was carried out. The following options were examined: - formation of module as one-piece Ship's hull for long-term storage at Saida Bay; - formation of separated modules for long-term storage at Saida Bay; - complete dismantling of hull's structures, systems and equipment with packing all generated SRW into certified long-term storage containers. This paper contains description of options, research procedure, comparative analysis of options of decommissioning and dismantling (D and D) of nuclear technological support ships and its difference with dismantling of nuclear submarine. On the basis of the technical and economic assessment of FTB D and D options the least expensive on the first D and D stage and the least duration option is the option 1 (Formation of module as one-piece Ship's hull for long-term storage at Saida Bay). By the implementation of the given option there will be the need of large areas for modules storage at Saida Bay. It was not considered while working out

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

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

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

Management options for food production systems affected by a nuclear accident. Task 2: options for minimising the production of contaminated milk

International Nuclear Information System (INIS)

Smith, J.G.; Nisbet, A.F.; Mercer, J.A.; Brown, J.; Wilkins, B.T.

2002-01-01

This report describes an evaluation of three possible means by which the production of waste milk could be reduced following a nuclear accident. The three options studied are the reduction of contaminated pasture in the diet, the drying off of lactating dairy cattle and the slaughter of dairy cattle. The practicability of each of these is considered using criteria such as technical feasibility, capacity, cost, impact and acceptability, where appropriate. In theory reductions in waste milk arisings can be achieved with each option, however, there are a number of limitations associated with their practical application. (author)

Glossary of scientific and technical terms in atomic energy

International Nuclear Information System (INIS)

1986-01-01

In order to facilitate the task of Arabic speaking scientists in the field of nuclear energy, the Atomic Energy Commission of Syria assigned a committee constituted of leading physicists and chemists at Damascus University, the aim of the commission was to include the Arabic equivalent of the terms cited in English, French, Russian and Spanish in the glossary published by the United Nations, 1958 ''Atomic Energy Glossary of Technical Terms.'' The result of the committee's work was this glossary containing approximately 6000 terms in the field of nuclear energy which are given in Arabic, English, French, Russian and Spanish

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.

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.

Technical activities, 1990: Surface Science Division

International Nuclear Information System (INIS)

Powell, C.J.

1991-05-01

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

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...

A Digital Library for the National Advisory Committee for Aeronautics

Science.gov (United States)

Nelson, Michael L.

1999-01-01

We describe the digital library (DL) for the National Advisory Committee for Aeronautics (NACA), the NACA Technical Report Server (NACATRS). The predecessor organization for the National Aeronautics and Space Administration (NASA), NACA existed from 1915 until 1958. The primary manifestation of NACA's research was the NACA report series. We describe the process of converting this collection of reports to digital format and making it available on the World Wide Web (WWW) and is a node in the NASA Technical Report Server (NTRS). We describe the current state of the project, the resulting DL technology developed from the project, and the future plans for NACATRS.

Impact of ITER liquid metal design options on safety level and licensing - Sweden

International Nuclear Information System (INIS)

Harfors, C.; Devell, L.; Johansson, Kjell; Lundell, B.; Rolandsson, S.

1993-01-01

The safety level and licensability of five design options for ITER coolant, breeding material and structural material are assessed, with emphasis on some specified accident scenarios. The safety level is assessed in terms of barrier requirements and the feasibility to construct and qualify such a barrier. The licensability in Sweden of each design option is assessed based on the indicated safety level and on a judgement of the technical feasibility to construct and qualify the ITER tokamak itself, based on the selected design option. 20 refs

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

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

Valuation of exploration and production assets. An overview of real options models

International Nuclear Information System (INIS)

Dias, Marco Antonio Guimaraes

2004-01-01

This paper presents a set of selected real options models to evaluate investments in petroleum exploration and production (E and P) under market and technical uncertainties. First are presented some simple examples to develop the intuition about concepts like option value and optimal option exercise, comparing them with the concepts from the traditional net present value (NPV) criteria. Next, the classical model of Paddock, Siegel and Smith is presented, including a discussion on the practical values for the input parameters. The modeling of oil price uncertainty is presented by comparing some alternative stochastic processes. Other E and P applications discussed here are the selection of mutually exclusive alternatives under uncertainty, the wildcat drilling decision, the appraisal investment decisions, and the analysis of option to expand the production through optional wells

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

International Nuclear Information System (INIS)

2007-01-01

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

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.

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.

DISPOWER. A socio-economic analysis of technical solutions and practices for the integration of distributed generation

International Nuclear Information System (INIS)

Ten Donkelaar, M.; Scheepers, M.J.J.

2004-07-01

Socio-economic impacts of technical solutions and approaches that are being developed for the integration of distributed generation (DG) in electricity distribution systems are analyzed. For this analysis an inventory was made of technical options, solutions and approaches on the basis of a questionnaire that has been distributed among DG (technical) experts. The questionnaire was not meant to give an exhaustive overview, but to gain insight in the possible technical solutions, options and approaches and the economic interactions between different actors in the electricity market. The different technical options and solutions have been divided into four main categories. Four technologies, one of each category, have been studied in more detail to analyse their impact on the financial relationships between the actors in the distribution network. The four technologies are: wind power prediction tool (planning tool), grid control unit (power quality device), power operation and power quality management system (ICT device), and power storage device. To assess the impact of the investments in the proposed technologies on all actors involved (and different from the actor investing), an assessment tool has been developed to qualitatively identify the economic impacts of a number of these options. This assessment tool takes into account the financial transactions between the parties on the distribution network. The analysis also discusses the allocation of the economic value of certain benefits through contracts and economic network regulation

An exploration of options and functions of climate technology centres and networks. Discussion paper

International Nuclear Information System (INIS)

De Coninck, H.C.; Wuertenberger, L.; Cochran, J.; Cox, S.; Benioff, R.

2010-11-01

This paper responds to a request to UNEP from the UNFCCC Expert Group on Technology Transfer to examine operational modalities for climate technology centres and networks. The paper first discusses possible dimensions for the climate technology centre and network, and it reviews a number of existing networks and centres. It then distinguishes five options for the organizational structure and describes potential operational characteristics for each of these options. All options examined seek to build from existing climate and non-climate-related public and private technology centres, networks, and initiatives. Consistent with the UNFCCC negotiating text and draft technology decision, the paper evaluates potential implementation options and outcomes for each of the functions tentatively assigned to the climate technology centre and network, as well as selected functions of the technology executive committee. Approaches are offered for integrating delivery of these functions through coordinated programmes, and hypothetical examples are given to explain how the technology mechanism might add value in practice. The options presented in this paper are not an exhaustive treatment of potential structures or implementation approaches, and other approaches can be considered.

76 FR 27019 - Interagency Ocean Observation Committee, Meeting of the Data Management and Communications...

Science.gov (United States)

2011-05-10

... Observation Committee, Meeting of the Data Management and Communications Steering Team AGENCY: National Ocean... meeting of the IOOC's Data Management and Communications Steering Team (DMAC-ST). The DMAC-ST membership... the IOOC in December 2010 to assist with technical guidance with respect to the management of ocean...

In situ leaching of uranium: Technical, environmental and economic aspects

International Nuclear Information System (INIS)

1989-01-01

Within the framework of its activities in nuclear raw materials the International Atomic Energy Agency has convened a series of meetings to discuss various aspects of uranium ore processing technology, recovery of uranium from non-conventional resources and development of projects for the production of uranium concentrates including economic aspects. As part of this continuing effort to discuss and document important aspects of uranium production the IAEA convened a Technical Committee Meeting on Technical, Economic and Environmental Aspects of In-Situ Leaching. Although the use of this technique is limited by geological and economic constraints, it has a significant potential to produce uranium at competitive prices. This is especially important in the current uranium market which is mainly characterised by large inventories, excess production capability and low prices. This situation is not expected to last indefinitely but it is unlikely to change drastically in the next ten years or so. This Technical Committee Meeting was held in Vienna from 3 to 6 November 1987 with the attendance of 24 participants from 12 countries. Eight papers were presented. Technical sessions covered in-situ mining research, environmental and licensing aspects and restoration of leached orebodies; the technological status of in-situ leaching, the current status and future prospects of in-situ leaching of uranium in Member States, general aspects of planning and implementation of in-situ projects and the economics of in-situ leaching. Refs, figs and tabs

Report of the Education Technical Subcommittee on Food/Beverage Occupations.

Science.gov (United States)

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

Written by a technical committee of persons from industry, professional associations, and labor, as well as persons with special expertise, state officials, and educators in Oregon, this document lists the skills and knowledge required of employees in food and beverage occupations. It also identifies the industry standards (performance objectives)…

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

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*.

A technical review and assessment of the BEIR V [Biological Effects of Ionizing Radiation V] report

International Nuclear Information System (INIS)

1990-03-01

This report was prepared by the DOE BEIR V Technical Review Committee (TRC) to provide a technical review and assessment of the National Research Council's Bilogical Effects of Ionizing Radiation (BEIR) Committee's Report entitled ''Health Effects of Exposure to Low Levels of Ionizing Radiation'' (BEIR V). This report contains seven sections. The first section serves as an introduction and reviews the charge to the TRC. The second section is a chapter-by- chapter summary of the BEIR V Report. The third section is a summary of the risk estimates and conclusions of the BEIR V Committee for genetic effects, cancer induction, and in utero effects. The fourth section is a summary and analysis of the new scientific information used by the BEIR V Committee in developing its risk recommendations and conclusions. The fifth section is an assessment of the scientific information and methods used by the BEIR V Committee in developing their risk estimates and conclusions and an analysis of the key assumptions underlying the use of these risk estimates in risk assessment. The sixth section is the TRC'S assessment of the regulatory implications of the BEIR V risk estimates and conclusions for DOE nuclear operations. The seventh and final section is the TRC'S recommended actions for DOE's consideration concerning the BEIR V Report risk estimates and conclusions. 23 refs., 5 tabs

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...

77 FR 32639 - HIT Standards Committee and HIT Policy Committee; Call for Nominations

Science.gov (United States)

2012-06-01

... DEPARTMENT OF HEALTH AND HUMAN SERVICES HIT Standards Committee and HIT Policy Committee; Call for... Health Information Technology Policy Committee (HITPC). Name of Committees: HIT Standards Committee and HIT Policy Committee. General Function of the Committees: The HITSC is charged to provide...

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

Assessment of technical risks and R and D requirements for a magnetic confinement fusion fuel system. Final report

International Nuclear Information System (INIS)

DeFreece, D.A.

1983-11-01

This report documents a specific use and results of a novel technique for assessing the technical risks associated with the hardware development of a possible future commercial fusion power plant fuel system. 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. A technical risk assessment is the quantification of this risk. This Technical Risk Assessment (TRA) methodology was applied to a deuterium-tritium fuel system for a magnetic-confinement fusion power plant. The fuel system is defined to support a generic commercial reactor with at least two viable options for each critical subsystem. Each subsystem option is defined in detail including nominal performance requirements and subsystem interfaces. Subsystem experts were canvassed to obtain values for past, present and future technical performance parameters for each of the subsystem options. These forecasts are presented as probabilities of achieving given levels of performance in specific time periods for assumed funding scenarios. Several funding scenarios were examined to discern whether performance limitations are caused by funding or technology. A computerized Fuel System simulation is described which uses these subsystem performance parameter forecasts as inputs

75 FR 16461 - Meeting of the Mobile Sources Technical Review Subcommittee

Science.gov (United States)

2010-04-01

... Committee Act, Public Law 92- 463, notice is hereby given that the Mobile Sources Technical Review... Hotel Crystal City-National Airport, 300 Army Navy Drive, Arlington, VA 22202-2891. Phone 703-416-4100. The hotel is located three blocks from the Pentagon City Metro station, and shuttle buses are...

Technical democracy as a challenge to urban studies

DEFF Research Database (Denmark)

Farías, Ignacio; Blok, Anders

2016-01-01

What is technical democracy? And why does it matter for urban studies? As an introduction to this special feature, we address these questions by reflecting on To Our Friends, the 2014 manifesto of the Invisible Committee. We engage in particular its provocative diagnosis of the current situation......: power no longer resides in the modern institutions of representative democracy and the market economy; instead, power has become a matter of logistics, infrastructures and expertise. This diagnosis, we suggest, brings into view the challenge of technical democracy, that is, the democratization of techno......-scientific expertise and the instauration of forms of lasting collaboration among experts and laypeople. Urban politics, we claim, increasingly turns around socio-technical controversies and it is in terms of the politics of expertise that we should analyse and engage it. Building on Science and Technology Studies...

Concluding report by the committee of experts on the Brunsbuettel and Kruemmel nuclear power stations. Vattenfall to implement the set of measures and all recommendations

International Nuclear Information System (INIS)

Hassa, R.

2007-01-01

The independent Committee of Experts appointed by Vattenfall Europe after the events of June 28, 2007 in the Brunsbuettel and Kruemmel nuclear power stations concluded its investigations. The Committee had been asked to investigate and evaluate the situation associated with the events, and to elaborate proposals for improvement on this basis. The analysis by the Committee of Experts boils down to the finding that the Brunsbuettel and Kruemmel nuclear power stations represent a modern standard as far as design concepts and technical safety features are concerned. Besides technical preconditions, also the administrative features are in place for safe plant oepration. No indications were found of any deficits in safety culture which would justify doubt about the reliability of the operator or the staff responsible under the Atomic Energy Act, nor is there any doubt about the level of technical expertise. Vattenfall directly ordered the findings to be implemented by applying, for part of the technical measures, for implementation with the Kiel State Ministry for Social Affairs as the competent regulatory agency. The Vattenfall Group is going to establish a new safety organization and safety controlling for the nuclear power plants operated by the company. These measures are to ensure an optimum safety level and the highest safety standards. With Vattenfall, safety enjoys top priority. (orig.)

International Standards Development for Marine and Hydrokinetic Renewable Energy - Final Report on Technical Status

Energy Technology Data Exchange (ETDEWEB)

Rondorf, Neil E.; Busch, Jason; Kimball, Richard

2011-10-29

This report summarizes the progress toward development of International Standards for Marine and Hydrokinetic Renewable Energy, as funded by the U.S. Department of Energy (DOE) under the International Electrotechnical Commission (IEC) Technical Committee 114. The project has three main objectives: 1. Provide funding to support participation of key U.S. industry technical experts in 6 (originally 4) international working groups and/or project teams (the primary standards-making committees) and to attend technical meetings to ensure greater U.S. involvement in the development of these standards. 2. Provide a report to DOE and industry stakeholders summarizing the IEC standards development process for marine and hydrokinetic renewable energy, new international standards and their justifications, and provide standards guidance to industry members. 3. Provide a semi-annual (web-based) newsletter to the marine renewable energy community. The newsletter will educate industry members and stakeholders about the processes, progress, and needs of the US efforts to support the international standards development effort. The newsletter is available at www.TC114.us

Western Option - Disarmament of Russian Weapon Plutonium

International Nuclear Information System (INIS)

Tveiten, B.; Petroll, M.R.

2002-01-01

The Western Option concept describes an approach to the conversion of weapon-grade plutonium from Russian nuclear warheads under the special aspects of meeting the criteria of irreversible utilization. Putting this concept of plutonium conversion into non-weapon-grade material into effect would make a major contribution to improving security worldwide. This study is based on an agreement between the Russian Federation and the United States of America concluded in September 2000. It provides for the conversion of 34 t of weapon-grade plutonium in each of the two states. This goal is also supported by other G8 countries. While the United States performs its part of the agreement under its sole national responsibility, the Russian program needs financial support by Western states. Expert groups have pointed out several options as a so-called basic scenario. The funds of approx. US Dollar 2 billion required to put them into effect have not so far been raised. The Western Option approach described in this contribution combines results of the basic scenario with other existing experience and with technical solutions available for plutonium conversion. One of the attractions of the Western Option lies in its financial advantages, which are estimated to amount to approx. US Dollar 1 billion. (orig.) [de

Savannah River Plant Low-Level Waste Heat Utilization Project preliminary analysis. Volume II. Options for capturing the waste heat

International Nuclear Information System (INIS)

1978-11-01

Options for utilizing the heated SRP effluent are investigated. The temperature and availability characteristics of the heated effluent are analyzed. Technical options for energy recovery are discussed. A number of thermodynamic cycles that could generate electrical power using the energy in the heated SRP effluent are described. Conceptual designs for SRP application of two attractive options are presented. Other direct uses for the heated effluent, as heat sources for agriculture and aquaculture options are discussed

11 CFR 100.14 - State committee, subordinate committee, district, or local committee (2 U.S.C. 431(15)).

Science.gov (United States)

2010-01-01

... 11 Federal Elections 1 2010-01-01 2010-01-01 false State committee, subordinate committee, district, or local committee (2 U.S.C. 431(15)). 100.14 Section 100.14 Federal Elections FEDERAL ELECTION COMMISSION GENERAL SCOPE AND DEFINITIONS (2 U.S.C. 431) General Definitions § 100.14 State committee...

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.

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

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.

DOE Advanced Scientific Computing Advisory Committee (ASCAC) Report: Exascale Computing Initiative Review

Energy Technology Data Exchange (ETDEWEB)

Reed, Daniel [University of Iowa; Berzins, Martin [University of Utah; Pennington, Robert; Sarkar, Vivek [Rice University; Taylor, Valerie [Texas A& M University

2015-08-01

On November 19, 2014, the Advanced Scientific Computing Advisory Committee (ASCAC) was charged with reviewing the Department of Energy’s conceptual design for the Exascale Computing Initiative (ECI). In particular, this included assessing whether there are significant gaps in the ECI plan or areas that need to be given priority or extra management attention. Given the breadth and depth of previous reviews of the technical challenges inherent in exascale system design and deployment, the subcommittee focused its assessment on organizational and management issues, considering technical issues only as they informed organizational or management priorities and structures. This report presents the observations and recommendations of the subcommittee.

Endovascular therapy options in femoro-popliteal PAD; Endovaskulaere Therapieoptionen bei femoropoplitealer pAVK

Energy Technology Data Exchange (ETDEWEB)

Brechtel, Klaus [Universitaetsklinikum Tuebingen (Germany). Abt. fuer Diagnostische und Interventionelle Radiologie

2010-09-15

The endovascular treatment of femoro-popliteal PAD is still challenging. The number of endovascular procedures in this vessel segment has increased over the past years. Despite new technologies, the outcome of endovascular therapy in terms of durability is still weak. In the meantime, the latest developments are progressing, such as the combination of mechanical angioplasty and drug delivery. Additionally, there are former techniques, such as debulking by atherectomy, which have been technically improved and now contribute to modern concepts of endovascular treatment. This article provides an overview on treatment indications and technical options including the latest technical developments. (orig.)

State-of-the-art and main options to improve fuel-energy complex of ferrous metallurgy

Energy Technology Data Exchange (ETDEWEB)

Rozenblit, G I; Pashkov, V D; Romanov, G M

1981-01-01

In 1980, the State Institute for the Design and Planning Metallury (Gripromez), elaborated ''The main options of Fuel and energy resources conservation (FERG) in ferrous metallurgy of the USSR program of works for the period 1981-1985 and up to 1990''. The Gipromez technical committee recommended: 1) elaborating feasibility studies and reports, developing branch schemes and starting complexes to separate out FERC measures; 2) inclusion of the FERC measures at the starting complexes as the first stages of main projects construction; 3) that the Ministy of Ferrous Metallurgy of the USSR, general designers and enterprises reconsider the starting complexes of the projects constructed during the present five-year period and incorporate in them the urgent FERC actions on heat-utilizing facilities. Changing the steel smelting process structure through more extensive use of the converter process and installation of continuous blank casting allows achievement of considerable fuel conservation, some 4 m trf per year as compared with its consumption in the scheme of open-hearth furnace - blooming mill (slabbing mill). During the 11th five-year-plan period introduction of metallurgy plant. An installation with discharge of the converter gas without its afterburning and successive utilization as a fuel in the converter shop of the Novolipetsk is planned.

Low-frequency electrical dosimetry: research agenda of the IEEE International Committee on Electromagnetic Safety.

Science.gov (United States)

Reilly, J Patrick; Hirata, Akimasa

2016-06-21

This article treats unsettled issues in the use of numerical models of electrical dosimetry as applied to international limits on human exposure to low-frequency (typically  IEEE-ICES (International Committee on Electromagnetic Safety) Technical Committee 95. The paper discusses 25 issues needing attention, fitting into three general categories: induction models; electrostimulation models; and human exposure limits. Of these, 9 were voted as 'high priority' by members of Subcommittee 6. The list is presented as a research agenda for refinements in numerical modeling with applications to human exposure limits. It is likely that such issues are also important in medical and electrical product safety design applications.

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

FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

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

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program

International Nuclear Information System (INIS)

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01

This document provides guidance for the revision of DOE Order 5820.2A, ''Radioactive Waste Management.'' Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee

OIL AND GAS FUTURES AND OPTIONS MARKET

Directory of Open Access Journals (Sweden)

Ante Nosić

2017-01-01

Full Text Available Energy mineral resources markets are represented by complex supply and demand ratios which are depending on different factors such as technical (transport and geopolitical. The main specific of energy markets is represented by an uneven geographic distribution of hydrocarbon reserves and exploration on one hand and energy consumption on the other. World oil markets, although geographically localized, because of specific market trade, represent unique global market with decreasing price difference. Price differences are result of development of a transport possibilities of oil supply. Development of transport routes of natural gas and increasing number of liquefied natural gas terminals in the world give pressure to natural gas market and its integration into global gas market. Integration of regional gas markets into a common European gas market is main energy policy of EU concerning natural gas. On the other hand, there are still significant price differences on some markets (e.g. United States of America - South East Asia. Development of global energy markets is enabled by development of a futures and options contracts of an energy trade which have replaced bilateral contract deals between producers and consumers. Futures contracts are standardized contracts traded on exchanges. Buyer agrees to buy certain quantity of stock for an agreed upon price and with some future delivery date. Option is a contract which gives a buyer the option of the right to buy (or sell, depending on the option an asset at predetermined price and at a later date. Stocks price risk can be managed with the purchase and selling futures and options contracts. This paper deals with futures and options energy markets and their market strategies.

Multi-criteria evaluation for CHP system options

International Nuclear Information System (INIS)

Pilavachi, P.A.; Roumpeas, C.P.; Minett, S.; Afgan, N.H.

2006-01-01

Several Combined Heat and Power (CHP) system options have been considered for evaluation with respect to the end-user requirements. These included Internal Combustion Engines (Otto and Diesel), Gas Turbines, Steam Turbines and Combined Cycles covering a wide range of electrical output. Data have been obtained from literature and the CHP systems have been evaluated using different criteria such as overall efficiency, investment cost, fuel cost, electricity cost, heat cost, CO 2 production and footprint. A multi-criteria method is used with an agglomeration function based on the statistical evaluation of weight factors. The technical, economic and social aspects of each system have been evaluated in an integrated manner and the results have been compared by means of the Sustainability Index. Based on the above criteria and depending on the user requirements, the best CHP system options have been established

Designing flexible engineering systems utilizing embedded architecture options

Science.gov (United States)

Pierce, Jeff G.

This dissertation develops and applies an integrated framework for embedding flexibility in an engineered system architecture. Systems are constantly faced with unpredictability in the operational environment, threats from competing systems, obsolescence of technology, and general uncertainty in future system demands. Current systems engineering and risk management practices have focused almost exclusively on mitigating or preventing the negative consequences of uncertainty. This research recognizes that high uncertainty also presents an opportunity to design systems that can flexibly respond to changing requirements and capture additional value throughout the design life. There does not exist however a formalized approach to designing appropriately flexible systems. This research develops a three stage integrated flexibility framework based on the concept of architecture options embedded in the system design. Stage One defines an eight step systems engineering process to identify candidate architecture options. This process encapsulates the operational uncertainty though scenario development, traces new functional requirements to the affected design variables, and clusters the variables most sensitive to change. The resulting clusters can generate insight into the most promising regions in the architecture to embed flexibility in the form of architecture options. Stage Two develops a quantitative option valuation technique, grounded in real options theory, which is able to value embedded architecture options that exhibit variable expiration behavior. Stage Three proposes a portfolio optimization algorithm, for both discrete and continuous options, to select the optimal subset of architecture options, subject to budget and risk constraints. Finally, the feasibility, extensibility and limitations of the framework are assessed by its application to a reconnaissance satellite system development problem. Detailed technical data, performance models, and cost estimates

Report of the review committee on evaluation of the R and D subjects in the field of nuclear safety research

International Nuclear Information System (INIS)

2000-09-01

On the basis of the JAERI's Basic Guidelines for the Research Evaluation Methods and the Practices Manuals of the Institution Evaluation Committee and Research Evaluation Committee, the Ad Hoc Review Committee on Nuclear Safety Research composed of twelve experts was set up under the Research Evaluation Committee of the JAERI in order to review the R and D subjects to be implemented for five years starting in FY2000 in the Nuclear Safety Research Center (Department of Reactor Safety Research, Department of Fuel Cycle Safety Research and Department of Safety Research Technical Support). The Ad Hoc Review Committee meeting was held on January 20, 2000. According to the review methods including review items, points of review and review criteria, determined by the Research Evaluation Committee, the review was conducted based on the research plan documents submitted in advance and presentations by the Department Directors. The review report was submitted to the Research Evaluation Committee for further review and discussions in its meeting held on August 31, 2000. The Research Evaluation Committee recognized the review results as appropriate. This report describes the review results. (author)

Process to identify and evaluate restoration options

International Nuclear Information System (INIS)

Strand, J.; Senner, S.; Weiner, A.; Rabinowitch, S.; Brodersen, M.; Rice, K.; Klinge, K.; MacMullin, S.; Yender, R.; Thompson, R.

1993-01-01

The restoration planning process has yielded a number of possible alternatives for restoring resources and services injured by the Exxon Valdez oil spill. They were developed by resource managers, scientists, and the public, taking into consideration the results of damage assessment and restoration studies and information from the scientific literature. The alternatives thus far identified include no action natural recovery, management of human uses, manipulation of resources, habitat protection and acquisition, acquisition of equivalent resources, and combinations of the above. Each alternative consists of a different mix of resource- or service-specific restoration options. To decide whether it was appropriate to spend restoration funds on a particular resource or service, first criteria had to be developed that evaluated available evidence for consequential injury and the adequacy and rate of natural recovery. Then, recognizing the range of effective restoration options, a second set of criteria was applied to determine which restoration options were the most beneficial. These criteria included technical feasibility, potential to improve the rate or degree of recovery, the relationship of expected costs to benefits, cost effectiveness, and the potential to restore the ecosystem as a whole. The restoration options considered to be most beneficial will be grouped together in several or more of the above alternatives and presented in a draft restoration plan. They will be further evaluated in a companion draft environmental impact statement

Opening Session - Introductory remarks for Workshop on Accident Tolerant Fuel. OECD/NEA Workshop on Accident Tolerant Fuels, Workshop Expectations

International Nuclear Information System (INIS)

Dujardin, Thierry; Gulliford, Jim; Massara, Simone; Pasamehmetoglu, K.

2013-01-01

The workshop opened with the welcome address from Th. Dujardin (OECD/NEA), NEA Deputy Director. Th. Dujardin recalled the integrated NEA response to the dramatic Fukushima-Daiichi events performed by three standing technical committees: the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH). J. Gulliford (OECD/NEA) placed the workshop in the context of the activities of the Nuclear Science Committee within the framework of the NEA response to Fukushima- Daiichi. K. Pasamehmetoglu (INL, US) explained the main goals of the workshop oriented towards defining requirements for selection among various options during the feasibility phase of the development process, and not towards identifying and proposing design solutions

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

Energy Technology Data Exchange (ETDEWEB)

1993-02-01

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

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

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...

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.

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

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.

The Management Advisory Committee of the Inspection Validation Centre. 2nd report

International Nuclear Information System (INIS)

1985-06-01

The document is the second report of the Management Advisory Committee of the Inspection Validation Centre (I.V.C.). The IVC is concerned with the ultrasonic inspection of the CEGB's proposed PWR reactor pressure vessel, and other components. The report deals with the technical progress since May 1984, and includes: interim validation, retrospective validation, examination of procedures, test assembly manufacture, interim validation of manual forging inspections, and validation facilities. (U.K.)

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…

Disposal/recovery options for brine waters from oil and gas production in New York State. Final report

Energy Technology Data Exchange (ETDEWEB)

Matsumoto, M.R.; Atkinson, J.F.; Bunn, M.D.; Hodge, D.S.

1996-03-01

Produced water from oil and gas operations, or brine as it is typically referred, may be characterized as being highly saline, with total dissolved solids greater than 100 g/L. If these bribes are disposed improperly there may be severe adverse environmental effects. Thus, it is important that brine be disposed using environmentally sound methods. Unfortunately, costs for the disposal of brine water are a significant burden to oil and gas producers in New York State. These costs and the relatively low market price of oil and natural gas have contributed to the decline in gas and oil production in New York State during the past 10 years. The objectives of this study were to evaluate new and existing options for brine disposal in New York State, examine the technical and economic merits of these options, and assess environmental impacts associated with each option. Two new disposal options investigated for New York State oil and gas producers included construction of a regional brine treatment facility to treat brine prior to discharge into a receiving water and a salt production facility that utilizes produced water as a feed stock. Both options are technically feasible; however, their economic viability depends on facility size and volume of brine treated.

Disposal/recovery options for brine waters from oil and gas production in New York State. Final report

International Nuclear Information System (INIS)

Matsumoto, M.R.; Atkinson, J.F.; Bunn, M.D.; Hodge, D.S.

1996-03-01

Produced water from oil and gas operations, or brine as it is typically referred, may be characterized as being highly saline, with total dissolved solids greater than 100 g/L. If these bribes are disposed improperly there may be severe adverse environmental effects. Thus, it is important that brine be disposed using environmentally sound methods. Unfortunately, costs for the disposal of brine water are a significant burden to oil and gas producers in New York State. These costs and the relatively low market price of oil and natural gas have contributed to the decline in gas and oil production in New York State during the past 10 years. The objectives of this study were to evaluate new and existing options for brine disposal in New York State, examine the technical and economic merits of these options, and assess environmental impacts associated with each option. Two new disposal options investigated for New York State oil and gas producers included construction of a regional brine treatment facility to treat brine prior to discharge into a receiving water and a salt production facility that utilizes produced water as a feed stock. Both options are technically feasible; however, their economic viability depends on facility size and volume of brine treated

Savannah River Plant Low-Level Waste Heat Utilization Project preliminary analysis. Volume III. Preferred utilization options

International Nuclear Information System (INIS)

1978-11-01

The technical, economic, environmental, and institutional considerations that must be resolved before implementing options to recover energy from the heated SRP effluent are examined. Detailed hypothetical siting options and expected economic returns are examined for power generation, prawn production, and one industrial park scenario. The likely indirect effects on regional population, income, taxes, and infrastructure requirements if the industrial park scenario is implemented are also projected. Recommendations for follow-on studies to make possible an informed go/no-go decision for implementing attractive waste heat options using reject SRP effluent are included

Preliminary Analysis of Helicopter Options to Support Tunisian Counterterrorism Operations

Science.gov (United States)

2016-04-27

helicopters from Sikorsky to fulfill a number of roles in counterterrorism operations. Rising costs and delays in delivery raised the question of...whether other cost-effective options exist to meet Tunisia’s helicopter requirement. Approach Our team conducted a preliminary assessment of...alternative helicopters for counterterrorism air assault missions. Any decision to acquire an aircraft must consider many factors, including technical

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.

Beyond form and functioning: Understanding how contextual factors influence village health committees in northern India.

Directory of Open Access Journals (Sweden)

Kerry Scott

Full Text Available Health committees are a common strategy to foster community participation in health. Efforts to strengthen committees often focus on technical inputs to improve committee form (e.g. representative membership and functioning (e.g. meeting procedures. However, porous and interconnected contextual spheres also mediate committee effectiveness. Using a framework for contextual analysis, we explored the contextual features that facilitated or hindered Village Health, Sanitation and Nutrition Committee (VHSNC functionality in rural north India. We conducted interviews (n = 74, focus groups (n = 18 and observation over 1.5 years. Thematic content analysis enabled the identification and grouping of themes, and detailed exploration of sub-themes. While the intervention succeeded in strengthening committee form and functioning, participant accounts illuminated the different ways in which contextual influences impinged on VHSNC efficacy. Women and marginalized groups navigated social hierarchies that curtailed their ability to assert themselves in the presence of men and powerful local families. These dynamics were not static and unchanging, illustrated by pre-existing cross-caste problem solving, and the committee's creation of opportunities for the careful violation of social norms. Resource and capacity deficits in government services limited opportunities to build relationships between health system actors and committee members and engendered mistrust of government institutions. Fragmented administrative accountability left committee members bearing responsibility for improving local health without access to stakeholders who could support or respond to their efforts. The committee's narrow authority was at odds with widespread community needs, and committee members struggled to involve diverse government services across the health, sanitation, and nutrition sectors. Multiple parallel systems (political decentralization, media and other village groups

Beyond form and functioning: Understanding how contextual factors influence village health committees in northern India.

Science.gov (United States)

Scott, Kerry; George, Asha S; Harvey, Steven A; Mondal, Shinjini; Patel, Gupteswar; Ved, Rajani; Garimella, Surekha; Sheikh, Kabir

2017-01-01

Health committees are a common strategy to foster community participation in health. Efforts to strengthen committees often focus on technical inputs to improve committee form (e.g. representative membership) and functioning (e.g. meeting procedures). However, porous and interconnected contextual spheres also mediate committee effectiveness. Using a framework for contextual analysis, we explored the contextual features that facilitated or hindered Village Health, Sanitation and Nutrition Committee (VHSNC) functionality in rural north India. We conducted interviews (n = 74), focus groups (n = 18) and observation over 1.5 years. Thematic content analysis enabled the identification and grouping of themes, and detailed exploration of sub-themes. While the intervention succeeded in strengthening committee form and functioning, participant accounts illuminated the different ways in which contextual influences impinged on VHSNC efficacy. Women and marginalized groups navigated social hierarchies that curtailed their ability to assert themselves in the presence of men and powerful local families. These dynamics were not static and unchanging, illustrated by pre-existing cross-caste problem solving, and the committee's creation of opportunities for the careful violation of social norms. Resource and capacity deficits in government services limited opportunities to build relationships between health system actors and committee members and engendered mistrust of government institutions. Fragmented administrative accountability left committee members bearing responsibility for improving local health without access to stakeholders who could support or respond to their efforts. The committee's narrow authority was at odds with widespread community needs, and committee members struggled to involve diverse government services across the health, sanitation, and nutrition sectors. Multiple parallel systems (political decentralization, media and other village groups) presented

Data Sharing: A New Editorial Initiative of the International Committee of Medical Journal Editors. Implications for the Editors´ Network

NARCIS (Netherlands)

Alfonso, Fernando; Adamyan, Karlen; Artigou, Jean-Yves; Aschermann, Michael; Boehm, Michael; Buendia, Alfonso; Chu, Pao-Hsien; Cohen, Ariel; Cas, Livio Dei; Dilic, Mirza; Doubell, Anton; Echeverri, Dario; Enç, Nuray; Ferreira-González, Ignacio; Filipiak, Krzysztof J.; Flammer, Andreas; Fleck, Eckart; Gatzov, Plamen; Ginghina, Carmen; Goncalves, Lino; Haouala, Habib; Hassanein, Mahmoud; Heusch, Gerd; Huber, Kurt; Hulín, Ivan; Ivanusa, Mario; Krittayaphong, Rungroj; Lau, Chu-Pak; Marinskis, Germanas; Mach, François; Moreira, Luiz Felipe; Nieminen, Tuomo; Oukerraj, Latifa; Perings, Stefan; Pierard, Luc; Potpara, Tatjana; Reyes-Caorsi, Walter; Rim, Se-Joong; Rødevand, Olaf; Saade, Georges; Sander, Mikael; Shlyakhto, Evgeny; Timuralp, Bilgin; Tousoulis, Dimitris; Ural, Dilek; Piek, J. J.; Varga, Albert; Lüscher, Thomas F.

2017-01-01

The International Committee of Medical Journal Editors (ICMJE) provides recommendations to improve the editorial standards and scientific quality of biomedical journals. These recommendations range from uniform technical requirements to more complex and elusive editorial issues including ethical

1997 report of the scientific evaluation committee of DAPNIA (Department of astrophysics, particle physics, nuclear physics and instrumentation)

International Nuclear Information System (INIS)

Anon.

1998-01-01

The DAPNIA is a department of CEA, its main characteristic is to manage scientific teams working on astrophysics, nuclear physics, elementary particles and instrumentation. Every 2 years DAPNIA's activities are submitted to an evaluation made by a scientific committee whose members are experts independent from CEA. This committee reviews the work done, gives an opinion about the options chosen for the projects to come and writes out a report. In 1997 the committee had a very positive opinion of the work done by DAPNIA teams. The contributions to various and important national or international programs have been successful, we can quote: Ulysse mission, soho, iso, integral for spatial programs, aleph, delphi, H1 at Hera, atlas, cms, na48, nomad, babar, antares for particle physics and spiral, smc, compass for nuclear physics. The committee advises DAPNIA to favour more contacts between the theoreticians and the experimentalists who work on quantum chromodynamics and hadron physics. The committee shows its concern about improving the balance between the means dedicated to instrumentation designing and those dedicated to the analysis and interpretation of the experimental data collected. (A.C.)

CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

International Nuclear Information System (INIS)

2008-01-01

The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

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…

Future European Expendable Launcher Options and Technology Preparation

OpenAIRE

Sippel, Martin; van Foreest, Arnold; Klevanski, Josef; Gerstmann, Jens; Dutheil, Jean-Philippe; Jäger, Markus; Philip, Peter

2008-01-01

The paper describes latest results of the most recent activities in Germany in the technical assessment of future European launcher architecture. In a joint effort of DLR-SART with German launcher industry a next generation upper-medium class expendable TSTO and options for new liquid fuel upper stages for the small VEGA-launcher are addressed. The WOTAN study has investigated fully cryogenic launchers as well as those with a combination of solid and cryogenic stages, fulfilling a requirement...

Denali, Tulip, and Option Inferior Vena Cava Filter Retrieval: A Single Center Experience.

Science.gov (United States)

Ramaswamy, Raja S; Jun, Emily; van Beek, Darren; Mani, Naganathan; Salter, Amber; Kim, Seung K; Akinwande, Olaguoke

2018-04-01

To compare the technical success of filter retrieval in Denali, Tulip, and Option inferior vena cava filters. A retrospective analysis of Denali, Gunther Tulip, and Option IVC filters was conducted. Retrieval failure rates, fluoroscopy time, sedation time, use of advanced retrieval techniques, and filter-related complications that led to retrieval failure were recorded. There were 107 Denali, 43 Option, and 39 Tulip filters deployed and removed with average dwell times of 93.5, 86.0, and 131 days, respectively. Retrieval failure rates were 0.9% for Denali, 11.6% for Option, and 5.1% for Tulip filters (Denali vs. Option p = 0.018; Denali vs. Tulip p = 0.159; Tulip vs. Option p = 0.045). Median fluoroscopy time for filter retrieval was 3.2 min for the Denali filter, 6.75 min for the Option filter, and 4.95 min for the Tulip filter (Denali vs. Option p Option p = 0.67). Advanced retrieval techniques were used in 0.9% of Denali filters, 21.1% in Option filters, and 10.8% in Tulip filters (Denali vs. Option p Option p Option filter when compared to both the Denali and Tulip filters. Retrieval of the Denali filter required significantly less amount of fluoroscopy time and use of advanced retrieval techniques when compared to both the Option and Tulip filters. The findings of this study indicate easier retrieval of the Denali and Tulip IVC filters when compared to the Option filter.

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)

Harmonized technical standards in the nuclear field

International Nuclear Information System (INIS)

Carbone, Ferdinando

1976-01-01

The need was felt of harmonizing and gradually standardizing technical norms, from the well-known Anglo-Saxon type codes of practice to the equally well-known recommendations of the International Commission on Radiological Protection (ICRP). The latter provide the basis for the Euratom Directives (basic standards), which, following their adoption, were embodied in the national laws of community Member countries. ISO (International Standardization Organization) is active in the nuclear technical regulations field, in particular through its Committee ISO/TC 85 ''Nuclear Energy'' at international level and, in Italy, through the National Italian Unification Agency (UNI) and its Nuclear Unification Commission (UNICEN). At its XI plenary meeting this body, on the proposal of the Secretary-General, set up a Study Group to promote revision of the regulation in force and coordination between legislation and development of UNICEN standards, considered as a set of integrative industrial technical standards. CISDEN, the Italian Nuclear Energy Forum (FIEN) and other interested organizations have been invited to collaborate in this work. (N.E.A.)

48 CFR 552.217-71 - Notice Regarding Option(s).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Notice Regarding Option(s... Notice Regarding Option(s). As prescribed in 517.208(b), insert the following provision: Notice Regarding Option(s) (NOV 1992) The General Services Administration (GSA) has included an option to [Insert...

75 FR 62534 - Request for Nominations to the National Advisory Committee for the Development of Acute Exposure...

Science.gov (United States)

2010-10-12

... of complex and technical information, and have the ability to volunteer approximately 10 to 15 hours... appearance of a lack of impartiality; e. Skills working in advisory committees and panels, and f. Diversity....gov/oppt/aeg1/pubs/ethics.htm . List of Subjects Environmental protection, Hazardous substances, NAC...

Freight Advanced Traveler Information System (FRATIS) Dallas-Fort Worth : software architecture design and implementation options.

Science.gov (United States)

2013-05-01

This document describes the Software Architecture Design and Implementation Options for FRATIS : system. The demonstration component of this task will serve to test the technical feasibility of the : FRATIS prototype while also facilitating the colle...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-05-01

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

75 FR 51827 - Notice of a Meeting of a Working Group of the NIH Advisory Committee to the Director

Science.gov (United States)

2010-08-23

... Emerging Infectious Diseases Laboratories (NEIDL) at Boston University Medical Campus. The meeting will be... between the Blue Ribbon Panel and the National Research Council Committee on Technical Input (NRC... concerning this meeting, contact Ms. Kelly Fennington, Senior Health Policy Analyst, Office of Biotechnology...

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01

This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

The contribution of the CSNI Principal Working Group on Confinement of Accidental Radioactive Releases to the technical consensus and spreading of knowledge on severe accidents

International Nuclear Information System (INIS)

De Boeck, B.; Royen, J.

1999-01-01

The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) is an international committee made up of scientists and engineers. It was set up 1973 to develop and co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Committee's purpose is to foster international cooperation in nuclear safety amongst the Member countries. Five Principal Working Groups (PWG) operate under the leadership of CSNI. PWG4 is named 'Confinement of Accidental Radioactive Releases' and its main activities are State of the Art Reports, International Standard Problem exercises, Specialist Meetings and Technical Opinion Papers. Together with other groups of experts involved in severe accident work, PWG4 has strongly contributed to the understanding of phenomena and the development of the knowledge base in that area, to the resolution of technical issues, and to the dissemination of the results. Taking examples from the products of the work of PWG4, the paper shows how this working group fosters international co-operation in the area of severe accidents and their management, and contributes to the development of a technical consensus. (author)

ASME nuclear codes and standards: Recent technical initiatives

International Nuclear Information System (INIS)

Feigel, R. E.

1995-01-01

Although nuclear power construction is currently in a hiatus in the US, ASME and its volunteer committees remain committed to continual improvements in the technical requirements in its nuclear codes. This paper provides an overview of several significant recent revisions to ASME' s nuclear codes. Additionally, other important initiatives currently being addressed by ASME committees will be described. With the largest population of operating light water nuclear plants in the world and worldwide use of its nuclear codes, ASME continues to support technical advancements in its nuclear codes and standards. While revisions of various magnitude are an ongoing process, several recent revisions embody significant changes based on state of the art design philosophy and substantial industry experience. In the design area, a significant revisions has recently been approved which will significantly reduce conservatisms in seismic piping design as well as provide simplified design rules. Major revisions have also been made to the requirements for nuclear material manufacturers and suppliers, which should result in clearer understanding of this difficult administrative area of the code. In the area of Section XI inservice rules, substantial studies are underway to investigate the application of probabilistic, risked based inspection in lieu of the current deterministic inspection philosophy. While much work still is required in this area, it is an important potential application of the emerging field of risk based inspection

75 FR 33587 - Federal Advisory Committee; Department of Defense Wage Committee

Science.gov (United States)

2010-06-14

... Wage Committee AGENCY: Department of Defense (DoD). ACTION: Notice of closed meeting. SUMMARY: Pursuant... hereby given that the Department of Defense Wage Committee will meet on July 13, 2010, in Rosslyn... writing to the Chairman, Department of Defense Wage Committee, 4000 Defense Pentagon, Washington, DC 20301...

75 FR 44231 - Federal Advisory Committee; Department of Defense Wage Committee

Science.gov (United States)

2010-07-28

... Wage Committee AGENCY: Department of Defense (DoD). ACTION: Notice of closed meeting. SUMMARY: Pursuant... hereby given that a closed meeting of the Department of Defense Wage Committee will be held on August 24..., Department of Defense Wage Committee, 4000 Defense Pentagon, Washington, DC 20301- 4000. SUPPLEMENTARY...

75 FR 28786 - Federal Advisory Committee; Department of Defense Wage Committee

Science.gov (United States)

2010-05-24

... Wage Committee AGENCY: Department of Defense (DoD). ACTION: Notice of closed meeting. SUMMARY: Pursuant... hereby given that a closed meeting of the Department of Defense Wage Committee will be held on June 15..., Department of Defense Wage Committee, 4000 Defense Pentagon, Washington, DC 20301- 4000. SUPPLEMENTARY...

75 FR 40796 - Federal Advisory Committee; Department of Defense Wage Committee

Science.gov (United States)

2010-07-14

... Wage Committee AGENCY: Department of Defense (DoD). ACTION: Notice of closed meeting. SUMMARY: Pursuant... hereby given that a closed meeting of the Department of Defense Wage Committee will be held on August 10..., Department of Defense Wage Committee, 4000 Defense Pentagon, Washington, DC 20301- 4000. SUPPLEMENTARY...

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,…

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

International Nuclear Information System (INIS)

2001-06-01

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

Ontario Select Committee on Alternative Fuel Sources : Final Report

International Nuclear Information System (INIS)

Galt, D.

2002-06-01

On June 28, 2001, the Ontario Legislative Assembly appointed the Select Committee an Alternative Fuel Sources, comprised of representatives of all parties, with a broad mandate to investigate, report and offer recommendations with regard to the various options to support the development and application of environmentally sustainable alternatives to the fossil fuel sources already existing. The members of the Committee elected to conduct extensive public hearings, conduct site visits, attend relevant conferences, do some background research to examine a vast number of alternative fuel and energy sources that could be of relevance to the province of Ontario. A discussion paper (interim report) was issued by the Committee in November 2001, and the present document represents the final report, containing 141 recommendations touching 20 topics. The information contained in the report is expected to assist in the development and outline of policy and programs designed to specifically support alternative fuels and energy sources and applicable technologies. Policy issues were discussed in Part A of the report, along with the appropriate recommendations. The recommendations on specific alternative fuels and energy sources were included in Part B of the report. It is believed that the dependence of Ontario on traditional petroleum-based fuels and energy sources can be reduced through aggressive action on alternative fuels and energy. The benefits of such action would be felt in the area of air quality, with social, and economic benefits as well. 3 tabs

The feasibility study I on the blanket fuel options for the ATW/HYPER

Energy Technology Data Exchange (ETDEWEB)

Hwang, Woan; Lee, Byoung Oon; Lee, Bong Sang; Park, Won Seok; Meyer, M.K; Hayes, S.L

2001-01-01

The choice of a blanket fuel cycle technology and the fuel type for HYPER/ATW are important to develop an ADS with better economics, performance and safety. Even though several fuel types have been considered as an alternative of the blanket fuels for HYPER/ATW, the metal alloy and the dispersion fuels were selected as the candidate fuels for ADS, and the technical feasibilities for both fuels are evaluated in this report. General performance characteristics, fabrication abilities, technical aspects, safety aspects, economics, and non-proliferation aspects for each fuel type are reviewed and evaluated. And some technological problems are addressed in this report, focused on the development strategy, the roadmaps, and the flexibility to meet the missions and specific designs. This study has been performed at the first stage of conceptual design. Since it is under the lack of physical properties for each fuel material, no an attempt is made to select the best fuel option, but the more better fuel options are recommended.

The feasibility study I on the blanket fuel options for the ATW/HYPER

International Nuclear Information System (INIS)

Hwang, Woan; Lee, Byoung Oon; Lee, Bong Sang; Park, Won Seok; Meyer, M.K; Hayes, S.L.

2001-01-01

The choice of a blanket fuel cycle technology and the fuel type for HYPER/ATW are important to develop an ADS with better economics, performance and safety. Even though several fuel types have been considered as an alternative of the blanket fuels for HYPER/ATW, the metal alloy and the dispersion fuels were selected as the candidate fuels for ADS, and the technical feasibilities for both fuels are evaluated in this report. General performance characteristics, fabrication abilities, technical aspects, safety aspects, economics, and non-proliferation aspects for each fuel type are reviewed and evaluated. And some technological problems are addressed in this report, focused on the development strategy, the roadmaps, and the flexibility to meet the missions and specific designs. This study has been performed at the first stage of conceptual design. Since it is under the lack of physical properties for each fuel material, no an attempt is made to select the best fuel option, but the more better fuel options are recommended

A status and strategy for nuclear technical cooperation with the U.S.A and other countries in the region

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Kim, Young Min

1998-12-01

The seven Joint Coordination Committee between R.O.K. and other countries, including U.S. and Canada are currently in operation for peaceful use of atomic energy. Among these, the most amicable and fruitful committees are the R.O.K-U.S.A joint standing committee on nuclear energy cooperation (JSCNEC) and R.O.K-Canada joint coordinated committee. Various matters encompassing 8 policy matters, 14 technological cooperation matters, 13 nuclear safety cooperation matters and 6 safeguards matters were discussed at the 19th R.O.K.-U.S.A. JSCNEC held June 22-26 in Seoul and Taejon. Among these, matters related to KAERI are the 13 technical cooperation and 2 nuclear safety cooperation concerns. (author). 10 refs., 5 tabs., 2 figs

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.

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...

75 FR 50751 - Federal Advisory Committee; Department of Defense Wage Committee

Science.gov (United States)

2010-08-17

... Wage Committee ACTION: Notice of closed meetings. SUMMARY: Pursuant to the provisions of section 10 of... Wage Committee will meet on September 21, October 5, and October 19, 2010, in Rosslyn, VA. The meetings... meetings may be obtained by writing to the Chairman, Department of Defense Wage Committee, 4000 Defense...

Radiological impacts of spent nuclear fuel management options

International Nuclear Information System (INIS)

Riotte, H.; Lazo, T.; Mundigl, S.

2000-01-01

An important technical study on radiological impacts of spent nuclear fuel management options, recently completed by the NEA, is intended to facilitate informed international discussions on the nuclear fuel cycle. The study compares the radiological impacts on the public and on nuclear workers resulting from two approaches to handling spent fuel from nuclear power plants: - the reprocessing option, that includes the recycling of spent uranium fuel, the reuse of the separated plutonium in MOX fuel, and the direct disposal of spent MOX fuel; and the once-through option, with no reprocessing of spent fuel, and its direct disposal. Based on the detailed research of a group of 18 internationally recognised experts, under NEA sponsorship, the report concludes that: The radiological impacts of both the reprocessing and the non-reprocessing fuel cycles studied are small, well below any regulatory dose limits for the public and for workers, and insignificantly low as compared with exposures caused by natural radiation. The difference in the radiological impacts of the two fuel cycles studied does not provide a compelling argument in favour of one option or the other. The study also points out that other factors, such as resource utilisation efficiency, energy security, and social and economic considerations would tend to carry more weight than radiological impacts in decision-making processes. (authors)

Technical aspects of 3MV particle accelerator at GGV Bilaspur

International Nuclear Information System (INIS)

Mallik, C.

2013-01-01

The accelerator at GGV, Bilaspur is a 3 MV pelletron operating is Tandem mode. The talk will describe the technical aspects of the accelerator. It will also discuss the beam aspects of the pelletron and the feasibility options with the accelerator. (author)

Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 5/5

International Nuclear Information System (INIS)

2015-01-01

This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 5/5. The list includes the abbreviations for: • General Safety Requirements; • International Commission on Radiological Protection; • Intensive Contamination Survey Area; • International Experts Meeting; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of the Environment; • Nuclear Damage Compensation and Decommissioning Facilitation Corporation; • Nuclear Emergency Response Headquarters; • nuclear power plant; • Nuclear Safety Commission; • OECD Nuclear Energy Agency; • Special Decontamination Area; • Specific Safety Requirements; • technical cooperation; • Three Mile Island; • United Nations Scientific Committee on the Effects of Atomic Radiation

Report of the Wises Committee; Rapport du Comite des Sages

Energy Technology Data Exchange (ETDEWEB)

Castillon, P; Lesggy, M; Morin, E

2003-09-01

This report on the energy theme, calls in experts in different areas such economics, technologies, regulations, fiscality, geopolitics, regional, european and international approaches. Because of numerous constraints, interactions in the energy subject, the Wises Committee has wished to tackle in priority the subject under a point of view less technical, by insisting on the necessary sudden awareness of the public about stakes in the energy field, on the necessity to implement actions for energy efficiency without waiting for the crisis situations that will come from excess of energy consumption. (N.C.)

Systems for deep brain stimulation: review of technical features.

Science.gov (United States)

Amon, A; Alesch, F

2017-09-01

The use of deep brain stimulation (DBS) is an important treatment option for movement disorders and other medical conditions. Today, three major manufacturers provide implantable systems for DBS. Although the underlying principle is basically the same for all available systems, the differences in the technical features vary considerably. This article outlines aspects regarding the technical features of DBS systems. The differences between voltage and current sources are addressed and their effect on stimulation is shown. To maintain clinical benefit and minimize side effects the stimulation field has to be adapted to the requirements of the patient. Shaping of the stimulation field can be achieved by the electrode design and polarity configuration. Furthermore, the electric signal consisting of stimulation rate, stimulation amplitude and pulse width affect the stimulation field. Interleaving stimulation is an additional concept, which permits improved treatment outcomes. Therefore, the electrode design, the polarity, the electric signal, and the concept of interleaving stimulation are presented. The investigated systems can be also categorized as rechargeable and non-rechargeable, which is briefly discussed. Options for interconnecting different system components from various manufacturers are presented. The present paper summarizes the technical features and their combination possibilities, which can have a major impact on the therapeutic effect.

Recent development in the ASME O and M committee codes, standards, and guides

International Nuclear Information System (INIS)

Rowley, C.W.

1999-01-01

The ASME O and M Committee continues to expand and update its code, standards, and guides as contained in the ASME OM Code and the ASME OM Standards/Guides. This paper will describe recent changes to these two ASME documents, including technical inquiries, code cases, and the major reformat of the ASME OM Code 1998 Edition. Also two new Parts to the ASME OM S/G will be discussed: OM Part 23 and OM Part 24, which are close to being initially published. A third new Part to the ASME OM S/G has been authorized and has recently started to get organized: Part 26, 'Thermal Calibration of RTDs'. In addition this paper will describe the future plans for these two documents as provided in the O and M Committee Strategic Plan. (author)

Energy Materials Coordinating Committee (EMaCC). Fiscal year 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-31

The committee serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. This is accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops involving DOE and major contractors. 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. A FY 1994 budget summary table for each program is included. A directory and a keyword index is included at the end of this document.

Accredited Standards Committee N15 Developments And Future Directions

International Nuclear Information System (INIS)

Mathews, Caroline E.; May, Melanie; Preston, Lynne

2009-01-01

Accredited Standards Committee (ASC) N15, Methods of Nuclear Material Control, is sponsored by the Institute of Nuclear Materials Management (INMM) to develop standards for protection, control and accounting of special nuclear materials in all phases of the nuclear fuel cycle, including analytical procedures where necessary and special to this purpose, except that physical protection of special nuclear material within a nuclear power plant is not included. Voluntary consensus standards complement federal regulations and technical standards and fulfill an important role for the nuclear regulatory agencies. This paper describes the N15 standards development process, with INMM as the Standards Developing Organization (SDO) and the N15 Committee responsible for implementation. Key components of the N15 standards development process include ANSI accreditation; compliance with the ANSI Essential Requirements (ER), coordination with other SDOs, communication with stakeholders, maintenance of balance between interest categories, and ANSI periodic audits. Recent and future ASC N15 activities are discussed, with a particular focus on new directions in anticipation of renewed growth in nuclear power.