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

ITER technical advisory committee meeting

International Nuclear Information System (INIS)

Fujiwara, M.

1999-01-01

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

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

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

Report on the IAEA technical meeting on network of nuclear reaction data centres

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria); Henriksson, H [NEA Data Bank, Issy-les-Moulineaux (France)

2005-01-15

This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

Report on the IAEA technical meeting on network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.; Henriksson, H.

2005-01-01

This report summarizes the IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting), held at the Brookhaven National Laboratory, Upton, NY, USA from 4-7 October 2004. The meeting was attended by 20 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, status reports of the participating data centres, and a revised technical protocol for the cooperation of the network. (author)

Technical Meeting on Grading of the Application of Management System Requirements. Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of this Technical Meeting are threefold: - to share international experiences and lessons learned, as well as exchange views on best practices and strategies to overcome the difficulties encountered; - to review and discuss the draft technical report on 'Grading the Application of Management System Requirements, to allow the participants to contribute to the improvement of the document and to enrich it with practical examples; and - to strengthen the international networking of specialists in the field. The topics covered during the meeting will include: - Examples and case studies presented by participants from countries with nuclear facilities (mainly focused on NPPs, and, where appropriate, from research reactors, fuel cycle and waste management facilities) on grading the application of management system requirements and lessons learned. - Reviewing and improving the final draft of a technical report on 'Grading the Application of Management System Requirements', which will supersede the previous guidance: Grading of Quality Assurance Requirement: A Manual (Technical Reports Series No. 328)

The International Technical Safety Forum

CERN Multimedia

CERN Bulletin

2010-01-01

The International Technical Safety Forum is a meeting of safety experts from several physics labs in Europe and the US. Since 1998 participants have been meeting every couple of years to discuss common challenges in safety matters. The Forum helps them define best practices and learn from the important lessons learned by others.   The Forum's participants in front of building 40. This year, the meeting took place at CERN from 12 to 16 April. “This year's meeting covered subjects ranging from communication and training in matters of safety, to cryogenic safety, emergency preparedness and risk analysis”, explains Ralf Trant, head of the CERN Safety Commission and organiser of this year’s Forum. Radiation protection issues are not discussed at the meeting since they involve different expertise. The goal of the Forum is to allow participants to share experience, learn lessons and acquire specific knowledge in a very open way. Round-table discussions, dedicated time for ...

ITER technical advisory committee meeting at Garching

International Nuclear Information System (INIS)

Fujiwara, M.

1999-01-01

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

Report on the IAEA technical meeting on network of nuclear reaction data centres

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [IAEA Nuclear Data Section, Vienna (Austria)

2006-12-15

An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting) was held at IAEA Headquarters, Vienna, Austria, from 25 to 28 September 2006. The meeting was attended by 19 participants from 10 cooperating data centres of six Member States and two international organizations. A summary of the meeting is given in this report, along with the conclusions, actions, and status reports of the participating data centres. (author)

Report on the IAEA technical meeting on network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.

2006-12-01

An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (biennial Data Centre Heads Meeting) was held at IAEA Headquarters, Vienna, Austria, from 25 to 28 September 2006. The meeting was attended by 19 participants from 10 cooperating data centres of six Member States and two international organizations. A summary of the meeting is given in this report, along with the conclusions, actions, and status reports of the participating data centres. (author)

Report on the IAEA technical meeting on network of nuclear reaction data centres

International Nuclear Information System (INIS)

Pronyaev, V.G.; Schwerer, O.; Nichols, A.L.

2002-08-01

An IAEA Technical Meeting on the Network of Nuclear Reaction Data Centres (and the biennial Data Centre Heads' Meeting) was held at the OECD Nuclear Energy Agency, Issy-les-Moulineaux (near Paris), France, from 27 to 30 May 2002. The meeting was attended by 21 participants from 12 co-operating data centres of six Member States and two international organizations. This report contains the meeting summary, conclusions and actions, status reports of the participating data centres, and working papers considered. (author)

Forty-Second Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2009-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 41st TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meetings meeting arrangements for 2009, 2010, 2011 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2010-2011

Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (41st Annual Meeting). Working Material

International Nuclear Information System (INIS)

2008-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 40th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2008, 2009, 2010 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2008-2009

Minutes of the IFMIF technical meeting

International Nuclear Information System (INIS)

Nakamura, H.; Takeda, M.; Ida, M.; Maebara, S.; Yutani, T.; Sugimoto, M.

2004-03-01

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)

Sandia National Laboratories Internal Dosimetry Technical Basis Manual (Rev 4)

Energy Technology Data Exchange (ETDEWEB)

Goke, Sarah Hayes [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Elliott, Nathan Ryan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-09-01

The Sandia National Laboratories’ Internal Dosimetry Technical Basis Manual is intended to provide extended technical discussion and justification of the internal dosimetry program at SNL. It serves to record the approach to evaluating internal doses from radiobioassay data, and where appropriate, from workplace monitoring data per the Department of Energy Internal Dosimetry Program Guide DOE G 441.1C. The discussion contained herein is directed primarily to current and future SNL internal dosimetrists. In an effort to conserve space in the TBM and avoid duplication, it contains numerous references providing an entry point into the internal dosimetry literature relevant to this program. The TBM is not intended to act as a policy or procedure statement, but will supplement the information normally found in procedures or policy documents. The internal dosimetry program outlined in this manual is intended to meet the requirements of Federal Rule 10CFR835 for monitoring the workplace and for assessing internal radiation doses to workers.

Report on the IAEA technical meeting on the network of nuclear reaction data centres

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria)

2006-02-15

Results of the IAEA Technical meeting on the Network of Nuclear Reaction Data Centres held at the IAEA Headquarters, Vienna, Austria, 12 to 14 October 2005, are summarized in this report. The meeting was attended by 16 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, and status reports of the participating data centres. (author)

Report on the IAEA technical meeting on the network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.

2006-02-01

Results of the IAEA Technical meeting on the Network of Nuclear Reaction Data Centres held at the IAEA Headquarters, Vienna, Austria, 12 to 14 October 2005, are summarized in this report. The meeting was attended by 16 participants from 11 co-operating data centres of six Member States and two International Organizations. The report contains a summary of the meeting, the conclusions and actions, and status reports of the participating data centres. (author)

Forty-Fourth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2011-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 43rd TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Project&Budget (P&B) biennium 2012-2013; - Review the IAEA’s ongoing information exchange and coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

Results from Consultancy Meeting on Qualified Technical Centres

International Nuclear Information System (INIS)

Novakovic, Mladen

2017-01-01

Qualified Technical Centres (QTC) - Current Situation: •Many Member States (MS) need help dealing with DSRS; •Most seek assistance, which can include funding, through the IAEA; •Technical assistance is provided by various governmental organization and private companies (service providers = SP). QTC - Method of Delivery Numerous MS requests are pressing the IAEA’s capacity to assist: •Use qualified internal and external experts/contractors; •Limited pool for DSRS and need to expand; •Dedicated and specialized equipment; •Mobile hot cell; •Mobile tool kit; •Field operations; •Coordinated approach with Nuclear Security and Safety. Qualified Technical Centres for the Management of DSRS: •The challenge is to scale up the support for safe and secure management of DSRS; •Strengthen existing capacity of some MS to support others and make support more sustainable; •Expands the support that can be readily provided and meet the many needs of MS

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.

ITER technical meeting on nuclear analysis

International Nuclear Information System (INIS)

Khripunov, V.

2000-01-01

The ITER technical meeting on nuclear analysis was organized on 24-25 February 2000 at the ITER Joint Work Site in Garching. It was clear from the meeting that continuous nuclear analysis is a fundamental part of the design process

Development of nuclear technology through International Technical Cooperation programme: Malaysian experience

International Nuclear Information System (INIS)

Ainul Hayati Daud

1997-01-01

In the advent of new technologies and knowledge, countries need to rely on one another for progress and development. At the same time, new challenges to development, which are beyond the competence of any country to approach individually, have emerged. These have led to greater need for international co-operation, particularly among the developing countries. In Malaysia, international technical co-operation has contributed significantly towards the development of nuclear technology. Malaysia has received technical assistance through the multilateral, regional and bilateral co-operation. This assistance complements the efforts of the government to meet the primary objectives of science and technology programme, which are; intensification of R and D capacity and applications of technologies, both acquired and developed, in national development. Over the last one and a half decade, more than 70 projects valued almost USD 15 millions, were implemented under the Technical Assistance Programme of the International Atomic Energy Agency and the Bilateral Technical Assistance Programme of Japan and Australia. Malaysia also has benefited from the regional technical co-operation programme such Regional Co-operative Agreement for Asia and Pacific Region, United Nation Department Programme, International Nuclear Co-operation in Asia. While receiving assistance, Malaysia continues to assist other developing countries in their development efforts in the fields of nuclear technology, through the various international co-operation programmes. This report reviews the technical assistance received through the international co-operation and its contributions towards the development of nuclear technology in Malaysia for period 1980 - 1996

Forty-Sixth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were to: • Review the current status and the progress since the 45th TWG-FR meeting of FR and ADS technology development activities in IAEA Member States; • Review the activities (past, present and planned) of the IAEA’s project 1.1.5.3, “Support for fast reactor research, technology development and deployment” to ensure that they remain relevant to the needs of Member States; • Provide the experts group with updates to advise the IAEA on FR and ADS activities, including on proposals for relevant studies and reviews; • Serve as a means for exchanging information on national and international FR and ADS programmes; • Review the main achievements and outcomes of the “International Conference on Fast Reactors and Related Fuel Cycle: Safe Technologies and Sustainable Scenarios – FR13”, held on 4 – 7 March 2013 in Paris, France; • Promote the exchange of technical information by proposing topics for, and assisting in the organization of, IAEA Workshops and Technical Meetings for 2014-2015 and further, and • Review the IAEA’s concluded, on-going and planned coordinated research projects (CRPs) in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, Euratom, etc.)

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

Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2015-11-01

The demands on nuclear fuel have recently been increasing, and include transient regimes, higher discharge burnup and longer fuel cycles. This has resulted in an increase of loads on fuel and core internals. In order to satisfy these demands while ensuring compliance with safety criteria, new national and international programmes have been launched and advanced modelling codes are being developed. The Fukushima Daiichi accident has particularly demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure and also to predict fuel behaviour were an accident to occur.This publication presents the Proceedings of the Technical Meeting on Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents, which was hosted by the Nuclear Power Institute of China (NPIC) in Chengdu, China, following the recommendation made in 2013 at the IAEA Technical Working Group on Fuel Performance and Technology. This recommendation was in agreement with IAEA mid-term initiatives, linked to the post-Fukushima IAEA Nuclear Safety Action Plan, as well as the forthcoming Coordinated Research Project (CRP) on Fuel Modelling in Accident Conditions. At the technical meeting in Chengdu, major areas and physical phenomena, as well as types of code and experiment to be studied and used in the CRP, were discussed. The technical meeting provided a forum for international experts to review the state of the art of code development for modelling fuel performance of nuclear fuel for water cooled reactors with regard to steady state and transient conditions, and for design basis and early phases of severe accidents, including experimental support for code validation. A round table discussion focused on the needs and perspectives on fuel modelling in accident conditions. This meeting was the ninth in a series of IAEA meetings, which reflects Member States’ continuing interest in nuclear fuel issues. The previous meetings were held in 1980 (jointly with

High Burnup Fuel: Implications and Operational Experience. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2016-08-01

This publication reports on the outcome of a technical meeting on high burnup fuel experience and economics, held in Buenos Aires, Argentina in 2013. The purpose of the meeting was to revisit and update the current operational experience and economic conditions associated with high burnup fuel. International experts with significant experience in experimental programmes on high burnup fuel discussed and evaluated physical limitations at pellet, cladding and structural component levels, with a wide focus including fabrication, core behaviour, transport and intermediate storage for most types of commercial nuclear power plants

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

17 April 2008 - Head of Internal Audit Network meeting visiting the ATLAS experimental area with CERN ATLAS Team Leader P. Fassnacht, ATLAS Technical Coordinator M. Nessi and ATLAS Resources Manager M. Nordberg.

CERN Multimedia

Mona Schweizer

2008-01-01

17 April 2008 - Head of Internal Audit Network meeting visiting the ATLAS experimental area with CERN ATLAS Team Leader P. Fassnacht, ATLAS Technical Coordinator M. Nessi and ATLAS Resources Manager M. Nordberg.

Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Technical Exchange Meeting

Energy Technology Data Exchange (ETDEWEB)

Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-09-01

During FY13, the INL developed an advanced SMR PRA framework which has been described in the report Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Detailed Technical Framework Specification, INL/EXT-13-28974 (April 2013). In this framework, the various areas are considered: Probabilistic models to provide information specific to advanced SMRs Representation of specific SMR design issues such as having co-located modules and passive safety features Use of modern open-source and readily available analysis methods Internal and external events resulting in impacts to safety All-hazards considerations Methods to support the identification of design vulnerabilities Mechanistic and probabilistic data needs to support modeling and tools In order to describe this framework more fully and obtain feedback on the proposed approaches, the INL hosted a technical exchange meeting during August 2013. This report describes the outcomes of that meeting.

Report on the consultants' meeting on co-ordination of the nuclear reaction data centres. (Technical aspects)

International Nuclear Information System (INIS)

Schwerer, O.; Lammer, M.; Pronyaev, V.G.

1999-08-01

This report summarizes the 1999 Co-ordination Meeting on Technical Aspects of the Co-operation of the Nuclear Reaction Data Centres, hold at the IAEA Headquarters in Vienna, Austria, 18 to 20 May 1999. The meeting was attended by scientists from 11 Nuclear Data Centres from 7 Member States and 2 International Organizations. The present document contains a meeting summary, the conclusions and actions, and progress reports of the Participating Data Centres. (author)

Fifth technical meeting on quality

International Nuclear Information System (INIS)

Girard, A.

1998-01-01

This article reports on the 5th Technical Meeting on Quality which was held in San Diego on 20-22 October 1997 and which was attended by representatives of the Home and Joint Central Team and of manufacturers currently involved in the Large R and D projects. The meeting made progress towards the finalization of the ITER Quality Manual document for inclusion in the Final Design Report and the definition of the quality necessary for ITER procurement and construction

Quality control procedures applied to nuclear instruments. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2008-11-01

Quality Control (QC), test procedures for Nuclear Instrumentation are important for assurance of proper and safe operation of the instruments, especially with regard to equipment related to radiological safety, human health and national safety. Correct measurements of radiation parameters must be ensured, i.e., accurate measurement of the number of radioactive events, counting times and in some cases accurate measurements of the radiation energy and occurring time of the nuclear events. There are several kinds of testing on nuclear instruments, for example, type-testing done by suppliers, acceptance testing made by the end users, Quality Control tests after repair and Quality Assurance/Quality Controls tests made by end-users. All of these tests are based in many cases on practical guidelines or on the experience of the own specialist, the available standards on this topic also need to be adapted to specific instruments. The IAEA has provided nuclear instruments and supported the operational maintenance efforts of the Member States. Although Nuclear Instrumentation is continuously upgraded, some older or aged instruments are still in use and in good working condition. Some of these instruments may not, however, meet modern requirements for the end-user therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. As a result, new instrumentation which is not commercially available, or modernized/refurbished instruments, need to be tested or verified with QC procedures to meet national or international certification requirements. A technical meeting on QC procedures applied to nuclear instruments was organized in Vienna from 23 to 24 August 2007. Existing and required QC test procedures necessary for the verification of operation and measurement of the main characteristics of nuclear instruments was the focus of discussion at this meeting. Presentations made at the technical meeting provided

IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the technical meeting were to: • exchange information between the Member States/International Organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • present and discuss the Member States’/International Organizations’ policies and conditions for releasing to the IAEA both publicly available and confidential information on fast neutron systems; • collect data on fast neutron systems provided by participating Member States/International Organizations and encourage participants to contribute in data collection; • provide recommendations for further IAEA initiatives in the field of fast reactor knowledge preservation

Physics and technology of inertial fusion energy targets chambers and drivers. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-09-01

The third IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers took place 11-13 October 2004 in the Yousung Hotel Daejon, Republic of Korea. The first meeting was held in Madrid, Spain, 7-9 June 2000, and the second one in San Diego, California, 17-19 June 2002. Nuclear fusion has the promise of becoming an abundant energy source with good environmental compatibility. Excellent progress has been made in controlled nuclear fusion research on both magnetic and inertial approaches for plasma confinement. The IAEA plays a pro-active role to catalyze innovation and enhance worldwide commitment to fusion. This is done by creating awareness of the different concepts of magnetic as well as inertial confinement. The International Fusion Research Council (IFRC) supports the IAEA in the development of strategies to enhance fusion research in Member States. As part of the recommendations, a technical meeting on the physics and technology of inertial fusion energy (IFE) was proposed in one of the council meetings. The objective of the technical meeting was to contribute to advancing the understanding of targets and chambers for all proposed inertial fusion energy power plant designs. The topics to be covered were: Target design and physics, chamber design and physics, target fabrication injection and Tritium handling, assessment of safety, environment and economy aspect of IFE. It was recognized by the International Advisory Committee that the scope of the meeting should also include fusion drivers. The presentations of the meeting included target and chamber physics and technology for all proposed IFE plant concepts (laser driven, heavy-ion driven, Z-pinches, etc.). The final Research Coordination Meeting of the Coordinated Research Project on Elements of Power Plant Design for Inertial Fusion Energy, including further new results and achievements, followed the technical meeting. Twenty-nine participants from 12 countries participated

International Scientific and Technical Organisations

International Nuclear Information System (INIS)

Nunez-Lagos Rogla, R.

2003-01-01

The nuclear scientific and technical world is well aware of the EURATOM and IAEA activities but usually other international scientific and technical organisations relevant for their ordinary work are unknown. In this article three international organisations are described briefly, the International Union of Pure and Applied Physics (IUPAP). International Union of Pure and Applied chemistry (IUPAC) and the international council of Science (ICSU). (Author)

International Technical Working Group Cooperation to Counter Illicit Nuclear Trafficking

International Nuclear Information System (INIS)

Smith, D K; Niemeyer, S

2004-01-01

The Nuclear Smuggling International Technical Working Group (ITWG) is an international body of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking

Reference data libraries for nuclear applications - ENSDF. Summary report of technical meeting

International Nuclear Information System (INIS)

Balabanski, D.; Nichols, A.L.

2008-11-01

A Technical Meeting on 'Reference Data Libraries for Nuclear Applications - ENSDF' was held on 10- 11 November 2008 at the IAEA Headquarters, Vienna, Austria. All presentations, discussions and recommendations of this meeting are given in this report. The purpose of the meeting was to review and discuss possible new European input to the ENSDF database (Evaluated Nuclear Structure Data File). These inputs are comprehensive mass-chain evaluations that constitute updated recommendations for the nuclear structure and decay data of nuclides assembled on the basis of mass number. A meeting to address declining European effort was endorsed by the International Nuclear Data Committee in April 2008, and judged as essential in order to balance the share of responsibilities around the world for the maintenance of this important database. (author)

Outcome and Perspectives from the First IAEA International Technical Meeting on Statistical Methodologies for Safeguards

International Nuclear Information System (INIS)

Norman, C.; Binner, R.; Peter, N. J.; Wuester, J.; Zhao, K.; Krieger, T.; Walczak-Typke, A.C.; Richet, S.; Portaix, C.G.; Martin, K.; Bonner, E.R.

2015-01-01

Statistical and probabilistic methodologies have always played a fundamental role in the field of safeguards. In-field inspection approaches are based on sampling algorithms and random verification schemes designed to achieve a designed detection probability for defects of interest (e.g., missing material, indicators of tampering with containment and other equipment, changes of design). In addition, the evaluation of verification data with a view to drawing soundly based safeguards conclusions rests on the application of various advanced statistical methodologies. The considerable progress of information technology in the field of data processing and computational capabilities as well as the evolution of safeguards concepts and the steep increase in the volume of verification data in the last decades call for the review and modernization of safeguards statistical methodologies, not only to improve the efficiency of the analytical processes but also to address new statistical and probabilistic questions. Modern computer-intensive approaches are also needed to fully exploit the large body of verification data collected over the years in the increasing number and diversifying types of nuclear fuel cycle facilities in the world. The first biennial IAEA International Technical Meeting on Statistical Methodologies for Safeguards was held in Vienna from the 16 to 18 October 2013. Recommendations and a working plan were drafted which identify and chart necessary steps to review, harmonize, update and consolidate statistical methodologies for safeguards. Three major problem spaces were identified: Random Verification Schemes, Estimation of Uncertainties and Statistical Evaluation of Safeguards Verification Data for which a detailed list of objectives and actions to be taken were established. Since the meeting, considerable progress was made to meet these objectives. The actions undertaken and their outcome are presented in this paper. (author)

INFOTECH `92: DOE Technical Information (TI) Meeting, October 21--23, 1992

Energy Technology Data Exchange (ETDEWEB)

Blanton, J.M.

1992-10-01

This proceedings contains papers presented at the 1992 Department of Energy (DOE) Technical Information Meeting held at the Office of Scientific and Technical Information (OSTI), Oak Ridge, Tennessee, October 21--23, 1992. It is composed of written presentation given orally at the meeting in either large-group or break-out sessions. The proceedings is provided as a reference tool for those who attended the meeting as well as an information document for those unable to attend. The annual DOE Technical Information meeting is designed for information professionals involved in the management of the Department`s scientific and technical information (STI). Speakers include members of the OSTI staff as well as DOE and DOE contractors and other invited specialists in the field of information. The major objective of the meeting is to provide a forum within the Department for discussing current and future information policies, trends, and management techniques as well as the technologies and standards available for managing and accessing scientific and technical information.

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

Report on the IAEA consultants' meeting on the co-ordination of nuclear reaction data centres (technical aspects)

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria)

2001-07-01

This report summarizes the results of the IAEA Consultants' Meeting on the Co-ordination of Nuclear Reaction Data Centres (Technical Aspects), held at the IAEA Headquarters, Vienna, Austria, 28 to 30 May 2001. The meeting was attended by 16 participants from 10 co-operating data centres from six Member States and two International Organizations. The report contains a meeting summary, the conclusions and actions, progress and status reports of the participating data centres and working papers considered at the meeting. (author)

Organization of the ITER Co-ordinated Technical Activities International Team

International Nuclear Information System (INIS)

2001-01-01

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

International technical working group cooperation to counter illicit nuclear trafficking

International Nuclear Information System (INIS)

Smith, D.K.; Niemeyer, S.

2004-01-01

The Nuclear Smuggling International Technical Working Group (ITWG) is an international group of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking. ITWG members include policy and decision makers, law enforcement personnel, and scientists with expertise in, and responsibility for, nuclear forensics. (author)

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

Report on the IAEA technical meeting on co-ordination of the network of nuclear reaction data centres

International Nuclear Information System (INIS)

Schwerer, O.

2003-08-01

Results of the IAEA Technical Meeting on the Co-ordination of the Network of Nuclear Reaction Data Centres held at the IAEA Headquarters, Vienna, Austria, 17 to 19 June 2003, are summarised in this report. The meeting was attended by 14 participants from 9 cooperating data centres of five member states and two International Organizations. A meeting summary, the conclusions and actions, progress and status reports of the participating data centres, and working papers considered at the meeting, are given in the relevant sections. (author)

Technical minutes of the eighth INDC meeting, Vienna, 6 - 10 October 1975

International Nuclear Information System (INIS)

Benzi, V.

1977-01-01

Neutron nuclear data (report on 11th four centre meeting; additional information from neutron data centres other than NDS; two years publication cycle of CINDA; international exchange and assessment of use of evaluated data); non-neutron nuclear data (progress reports on activities, services and coordination of ''non-neutron'' nuclear data centres and groups; report on meeting on charged particle nuclear data (CPND) for applications; discussion on recommendations from ''non-neutron'' nuclear data meetings April/May 1974, including plans for 1976 meetings); coordination of nuclear data activities (status of development of regional nuclear data centres and national data committees; neutron data for reactor dosimetry; FPND newsletter; WRENDA for fission, fusion and safeguards; nuclear data measurements in developing countries; status and NDS targets and samples program); progress reports on nuclear data measurements, facilities and evaluations (additions to submitted progress reports; reports on nuclear data activities in countries not represented on INDC); reports of Technical and Ad-hoc sub-committees; reports of policy sub-committees; meetings

IAEA technical meeting on 'Technical aspects of atomic and molecular data processing and exchange'. Summary report

International Nuclear Information System (INIS)

Humbert, Denis

2004-03-01

The proceedings of the IAEA Advisory Group Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (17th Meeting of A+M Data Centres and ALADDIN Network), held on 6-7 October, 2003 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange, and distribution are also presented. (author)

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

Energy Technology Data Exchange (ETDEWEB)

Pronyaev, V G; Nichols, A L; Tuli, J [eds.

2004-03-01

The IAEA Nuclear Data Section convened the 15th meeting of the Network of Nuclear Structure and Decay Data Evaluators at the IAEA Headquarters, Vienna, 10-14 November 2003. This meeting was attended by 23 scientists from 11 Member States concerned with the compilation, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, the recommendations, data centre reports and the various proposals considered, modified and agreed by the participants are contained within this document. Nuclear data are essential to the development, implementation and maintenance of all nuclear technologies. The international network of Nuclear Structure and Decay Data (NSDD) Evaluators is sponsored by the IAEA, and consists of evaluation groups and data service centers in several countries. This network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration is included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets. The results represent the recommended 'best values' for the various nuclear structure and decay data parameters. Recommended values are made available to users by means of various media, such as the world wide web, CD-ROMs, wall charts of the nuclides, handbooks, nuclear wallet cards and others. Participants discussed a wide range of technical matters, and the recommendations of improving the quality of NSDD evaluations. A list of actions was also prepared for implementation during the course of the next two years. NSDD members prepared many recommendations for the IAEA and the major evaluation centers, which are aimed at improving the technical support towards the network and streamlining the organization of work. These consensus conclusions include: the development and exchange of programming products; revision of

Geothermal Energy and the Eastern US: Technical Information Interchange Meeting, Minutes

Energy Technology Data Exchange (ETDEWEB)

None

1979-12-01

The technical interchange meeting documented here is the fourth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

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

Technical Aspects of Atomic and Molecular Data Processing and Exchange, 22nd Meeting of the A+M Data Centres Network. Summary Report of an IAEA Technical Meeting

International Nuclear Information System (INIS)

Chung, Hyun-Kyung

2013-12-01

This report summarizes the proceedings of the IAEA Technical Meeting on ''Technical Aspects of Atomic and Molecular Data Processing and Exchange'' (22nd Meeting of the A+M Data Centres Network) on 4-6 September 2013. Twelve participants from 8 data centres of 6 Member States attended the three-day meeting held at the IAEA Headquarters in Vienna. The report includes discussions on the data issues, meeting conclusions and recommendations and the abstracts of presentations presented in the meeting. (author)

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

IAEA technical meeting: Assess and co-ordinate modelling needs and data providers. Summary report

International Nuclear Information System (INIS)

Clark, R.E.H.

2004-05-01

This report briefly describes the proceedings, conclusions and recommendations of the Technical Meeting to 'Assess and Co-ordinate Modelling Needs and Data Providers', held on 4-5 December 2003. Eight international experts on atomic and molecular data related to fusion energy research activities participated in the meeting. Each participant reviewed the current status of their own speciality and current lines of research as well as anticipated needs in new data for nuclear fusion energy research. Current CRPs on related topics were reviewed. In light of current research activities and anticipated data needs for fusion, a detailed set of tasks appropriate for a new CRP was developed. This meeting completely fulfilled the specified goals. (author)

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

IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Working Material

International Nuclear Information System (INIS)

2011-01-01

The IAEA, within the framework of its Nuclear Energy Department’s Technical Working Group on Fast Reactors (TWG-FR), assists Member States activities in fast reactors technology development areas by providing an umbrella for information exchange [topical Technical Meetings (TMs), Workshops and large Conferences] and collaborative R&D [Coordinated Research Projects (CRPs)]. The Technical meeting on “Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors” was held from 21 – 22 December 2011 in Vienna, addressing Member States’ expressed needs of information exchange in the field of advanced fast reactor design features, with particular attention to innovative heat exchangers and steam generators. The Objective of the TM is to provide a global forum for in-depth information exchange and discussion on the most advanced concepts of heat exchangers and steam generators for fast reactors. More specifically, the objectives are: · Review of the status of advanced fast reactor development activities with special emphasis on design and performance of heat exchangers and steam generators; · Discuss requirements for innovative heat exchangers and steam generators; · Present results of studies and conceptual designs for innovative heat exchangers and steam generators; · Provide recommendations for international collaboration under the IAEA aegis. The meeting agenda of the meeting is in Annex I

Geothermal Energy and the Eastern US: Fifth technical information interchange meeting, Minutes

Energy Technology Data Exchange (ETDEWEB)

None

1980-12-01

The technical interchange meeting documented here is the fifth meeting where people interested in geothermal energy in the Eastern US have met to interchange technical information. These meetings are intended to assist all in the difficult task of balancing time and effort in doing their assigned jobs and keeping track of what others are doing in similar or related tasks. All of the aforementioned meetings have served their intended purpose and further regional and national meetings are sure to follow.

Technical Working Group on Career and Technical Education Meeting. Meeting Summary (Washington, DC, September 22, 2017)

Science.gov (United States)

Ahn, Judie

2017-01-01

On September 22, 2017, the National Center for Special Education Research (NCSER) and the National Center for Education Research (NCER) at the Institute of Education Sciences (IES) convened a group of experts in policy, practice, and research related to Career and Technical Education (CTE). The goal of the meeting was to seek input from…

Technical aspects of atomic and molecular data processing and exchange, 20. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

International Nuclear Information System (INIS)

Humbert, D.; Braams, B.J.

2010-01-01

The proceedings of the IAEA Advisory Group Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (20th Meeting of A+M Data Centres Network), 7-9 September 2009 at IAEA Headquarters in Vienna, are summarized. The meeting conclusions and recommendations on priorities in A+M data compilation and evaluation and on technical aspects of data processing and exchange are also presented. (author)

Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

International Nuclear Information System (INIS)

2003-01-01

36th Annual Meeting of the Technical Working Group on Fast Reactors, the IAEA Technical Meeting (TM) on 'Review of National Programmes on Fast Reactors and Accelerator Driven Systems (ADS)', hosted by the Korean Atomic Energy Research Institute (KAERI) was attended by TWG-FR Members and Advisers from the following Member States (MS) and International Organizations: Brazil, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, the United Kingdom, the United States of America, and the OECD/NEA. The objectives of the meeting were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 35th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2003 and 2004; 4) review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations. The participants made presentations on the status of the respective national programmes on FR and ADS development. A summary of the highlights for the period since the 35th TWG-FR Annual Meeting

Technical aspects of atomic and molecular data processing and exchange. 19. meeting of the A+M Data Centres and ALADDIN Network. Summary report of an IAEA technical meeting

International Nuclear Information System (INIS)

Humbert, D.

2008-05-01

The proceedings of the IAEA Technical Meeting on Technical Aspects of Atomic and Molecular Data Processing and Exchange (19th Meeting of A+M Data Centres and ALADDIN Network), held on 3-5 October, 2007 in Vienna, Austria, are briefly described. Conclusions and recommendations are presented concerning various proposed projects and their priorities involving A+M data compilation and evaluation and technical aspects of data processing, exchange, and distribution. (author)

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

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2007-06-01

The '9th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 26-27 March 2007 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database and make recommendations for actions for the next year. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

Technical Requirements For Reactors To Be Deployed Internationally For the Global Nuclear Energy Partnership

International Nuclear Information System (INIS)

Ingersoll, Daniel T.

2007-01-01

The Global Nuclear Energy Partnership (GNEP) seeks to create an international regime to support large-scale growth in the worldwide use of nuclear energy. Fully meeting the GNEP vision may require the deployment of thousands of reactors in scores of countries, many of which do not use nuclear energy currently. Some of these needs will be met by large-scale Generation III and III+ reactors (>1000 MWe) and Generation IV reactors when they are available. However, because many developing countries have small and immature electricity grids, the currently available Generation III(+) reactors may be unsuitable since they are too large, too expensive, and too complex. Therefore, GNEP envisions new types of reactors that must be developed for international deployment that are 'right sized' for the developing countries and that are based on technologies, designs, and policies focused on reducing proliferation risk. The first step in developing such systems is the generation of technical requirements that will ensure that the systems meet both the GNEP policy goals and the power needs of the recipient countries. Reactor systems deployed internationally within the GNEP context must meet a number of requirements similar to the safety, reliability, economics, and proliferation goals established for the DOE Generation IV program. Because of the emphasis on deployment to nonnuclear developing countries, the requirements will be weighted differently than with Generation IV, especially regarding safety and non-proliferation goals. Also, the reactors should be sized for market conditions in developing countries where energy demand per capita, institutional maturity and industrial infrastructure vary considerably, and must utilize fuel that is compatible with the fuel recycle technologies being developed by GNEP. Arrangements are already underway to establish Working Groups jointly with Japan and Russia to develop requirements for reactor systems. Additional bilateral and multilateral

IAEA technical meeting on fissile material strategies for sustainable nuclear energy

International Nuclear Information System (INIS)

Ganguly, Chaitanyamoy; Koyama, Kazutoshi

2005-01-01

A Technical Meeting (TM) on 'Fissile Material Management Strategies for Sustainable Nuclear Energy' was organized by the International Atomic Energy Agency (IAEA) in Vienna from 12 to 15 September 2005. Prior to the TM, three Working Groups (WG) composed of experts from 10 countries prepared Key Issues papers on: 1) Uranium Demand and Supply through 2050; 2) Back-end Fuel Cycle Options; and 3) Sustainable Nuclear Energy beyond 2050: Cross-cutting Issues. Some 36 papers, including 3 key issue papers, were presented during the TM in 3 different sessions. The present paper summarizes the deliberations of the TM. (author)

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

International Nuclear Information System (INIS)

Abriola, D.; Dimitriou, P.; Ricard-McCutchan, E.; Tuli, J.K.

2013-08-01

Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network consists of evaluation groups and data service centres in several countries. This Network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

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

Energy Technology Data Exchange (ETDEWEB)

Abriola, D.; Dimitriou, P. [IAEA Nuclear Data Section, Vienna (Austria); Ricard-McCutchan, E.; Tuli, J. K. [Brookhaven National Laboratory, Upton, NY (United States)

2013-08-15

Biennial meetings of the International Network of Nuclear Structure and Decay Data (NSDD) evaluators are held under the auspices of the IAEA. The Network consists of evaluation groups and data service centres in several countries. This Network has the objective of providing up-to-date nuclear structure and decay data for all known nuclides by evaluating all existing experimental data. Data resulting from this international evaluation collaboration are included in the Evaluated Nuclear Structure Data File (ENSDF) and published in the journals Nuclear Physics A and Nuclear Data Sheets (NDS). The results represent the recommended 'best values' for the various nuclear structure and decay data properties. These data and bibliographic details are also available through the World Wide Web, CD-ROM, wall charts of the nuclides, Nuclear Wallet Cards and other such media. The US efforts are coordinated by the Coordinating Committee of the US Nuclear Data Program. The ENSDF master database is maintained by the US National Nuclear Data Centre at Brookhaven National Laboratory, and these data are also available from other distribution centres including the IAEA Nuclear Data Section. Biennial meetings of the Network are sponsored by the IAEA Nuclear Data Section, and have the following objectives: (a) coordination of the work of all centres and groups participating in the compilation, evaluation and dissemination of NSDD; (b) maintenance of and improvements to the standards and rules governing NSDD evaluations; (c) review of the development and common use of computerized systems and databases maintained specifically for this activity. In those meetings detailed studies and discussions are undertaken over a five-day period. This document represents a summary of the Network meeting held at the Kuwait Foundation for the Advancement of Sciences (KFAS), Safat, Kuwait, from 27 to 31 January 2013. Thirty-six nuclear data specialists from seventeen countries attended this meeting to

Commercial products and services of research reactors. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2013-07-01

enhance the utilization of research reactors and their sustainability through financially viable services and international cooperation. In this report, reference is also made to a similar IAEA technical meeting on “Commercial Applications of Nuclear Analytical Techniques”, held in Vienna, Austria, from 23 to 26 November 2004, and a few recently updated papers from that meeting have been included here. This publication summarizes the individual reports presented during the above meetings, and details the overall findings and conclusions jointly identified and agreed upon by the meeting participants. This publication summarizes the individual reports presented during the above meetings and details the overall findings and conclusions jointly identified and agreed upon by the meeting participants. The individual papers are available via the drop-down menus on the left menu

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

Summary report of IAEA technical meeting on technical aspects of atomic and molecular data processing and exchange - 18th meeting of the A+M Data Centres and ALADDIN Network

International Nuclear Information System (INIS)

Hubert, D.

2006-01-01

The IAEA Technical Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange - 18th Meeting of A+M Data Centres and ALADDIN Network' was held on 10-11 October 2005, in Vienna, Austria. The discussions and presentations focused on the priorities in A+M data compilation and evaluation, and are summarized in this report. Conclusions and recommendations on the technical aspects of data processing, exchange and distribution are also presented. (author)

Establishment of A+M Computer Code Network. Summary report of IAEA technical meeting

International Nuclear Information System (INIS)

Clark, R.E.H.

2006-01-01

Eleven international experts on computational aspects of atomic and molecular data for fusion energy research participated in a technical meeting arranged to discuss the establishment of an A and M Computer Code Network, and held at IAEA Headquarters on 23-25 May 2005. Each participant reviewed the current status of their own speciality and current lines of research, as well as anticipated needs in new data for nuclear fusion energy research. A preliminary method for making these valuable resources more readily available was outlined, and implementation will proceed. Several of the computational tools presented are already available through Internet connections. All the goals of the meeting were achieved, and every participant indicated a desire to see more collaboration and cooperation in fulfilling the A and M data needs for fusion. The discussions, conclusions and recommendations of the meeting are briefly described in this report. (author)

Tumor radiosensitizers - current status of development of various approaches: Report of an International Atomic Energy Agency meeting

DEFF Research Database (Denmark)

Horsman, Michael Robert; Bohm, Lothar; Margison, Geoffrey P.

2006-01-01

PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those well-established in clinical practice, that operated through a variety of mechanisms to sensitize tumors to radiation and (2) to compare...... and contrast their tumor efficacy, normal tissue toxicity, and status of development regarding clinical application. The aim was to advise the IAEA as to which developing agent or class of agents would be worth promoting further, by supporting additional laboratory research or clinical trials...... and for clinical trials that would be suitable for industrialized countries, as well as trials that were considered more appropriate for developing countries.PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those...

Proceedings of the Efficient Separations and Processing Cross-Cutting Program Annual Technical Exchange Meeting

International Nuclear Information System (INIS)

1995-01-01

This document contains summaries of technology development presented at the 1995 Efficient Separations and Processing Cross-Cutting Program (ESP) Annual Technical Exchange Meeting. The ESP is sponsored by the US Department of Energy's Office of Environmental Management (EM), Office of Technology Development. The meeting is held annually to promote a free exchange of ideas among technology developers, potential users (for example, EM focus areas), and other interested parties within EM. During this meeting, developers of ESP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Presenters are asked to address the following areas: Target waste management problem, waste stream, or data need; scientific background and technical approach; technical accomplishments and resolution of technical issues; schedule and strategy for commercializing and implementing the technology or acquiring needed data; potential alternate applications of the technology or data, including outside of DOE/EM. The meeting is not a program review of the individual tasks or subtasks; but instead focuses on the technical aspects and implementation of ESP-sponsored technology or data. The meeting is also attended by members of the ESP Technical Review Team, who have the opportunity at that time to review the ESP as a whole

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.

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

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

Internal dosimetry technical basis manual

International Nuclear Information System (INIS)

1990-01-01

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs

Internal dosimetry technical basis manual

Energy Technology Data Exchange (ETDEWEB)

1990-12-20

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

2011 Residential Energy Efficiency Technical Update Meeting Summary Report

Energy Technology Data Exchange (ETDEWEB)

none,

2011-11-01

This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

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

International scientific consensus on medical plantar pressure measurement devices: technical requirements and performance

Directory of Open Access Journals (Sweden)

Claudia Giacomozzi

2012-01-01

Full Text Available BACKGROUND: Since 2006, the Italian National Institute of Health (ISS has been conducting independent scientific activities to standardize the technical assessment of plantar pressure measurement devices (PMDs. MATERIAL AND METHODS: On the basis of the ISS results, in 2010 the Pedobarographic Group of the International Foot and Ankle Biomechanics community (i-FAB-PG promoted a consensus activity about the main technical requirements for the appropriate use of PMDs. The activity relied on a moodlebased on-line forum, documents exchange, discussions, reviews, meetings and a final survey. RESULTS: The participation of clinical and technical researchers, users, and manufacturers, contributed to the delivery of the hereby reported recommendations which specifically regard Medical PMDs in the form of platforms. CONCLUSIONS: The i-FAB-PG community reached overall agreement on the recommendations, with a few minor objections which are reported and commented in the document. RELEVANCE: The present document, the highest result achievable within a small scientific community, will hopefully represent the starting point of the wider process of establishing official international guidelines or standards, within scientific communities and standardization organizations.

Internal auditors meet at CERN

CERN Multimedia

2008-01-01

What does CERN have in common with INTERPOL? The answer: the challenge of managing a complex international organisation operating outside national regulations. Participants of the internal audit conference had the opportunity to visit ATLAS.On 17th &18th April CERN hosted a meeting for the Internal Audit Heads of some of the most famous international organisations in the world. Sixteen organisations were represented at the conference, including the European Commission, INTERPOL, the European Central Bank, the OECD, the European Space Agency (ESA), NATO and the European Organisation for Astronomical Research in the Southern Hemisphere (ESO). The objective of this annual meeting is to share best practices and benchmark performance in the fields of auditing, organizational governance, risk management and internal controls. International organisations, due to their specific legal status and the absence of applicable national legisl...

Proceedings of the 24th NSRR technical review meeting

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi; Fuketa, Toyoshi; Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-09-01

The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting. (author)

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...

XXIX International Meeting on Fundamental Physics, Sitges, Barcelona, Spain, 5-9 February, 2001

International Nuclear Information System (INIS)

Fonseca, V.; Dobado, A.

2001-01-01

The XXIX International Winter Meeting on Fundamental Physics took place in Sitges, Barcelona, Spain, from 5 to 9 February, 2001. The meeting was organized by the Universidad Complutense de Madrid (UCM) in collaboration with CIEMAT. It was supported by the Programa Nacional de Fisica de Altas Energias, by UCM and CIEMAT. As in previous editions, it brought together researchers working in experimental and theoretical Particle and Astroparticle Physics. More than seventy physicists from several countries participated in the Meeting. General talks, most recent results and time for physics discussions were considered in the program. In parallel to the development of the Meeting several other events took place. These events included a meeting to study the future of the Spanish Program of Advanced Studies in Theoretical High Energy Physics, an informal meeting to study the future for detection of high energy neutrino beams with underground detectors in the Canary Islands and another one concerning the PDGE /Proyecto Data Grid Espana). In addition we had the last day a special seminar in the honour of the 60th anniversary of Professor Yndurain. Francisco J. Yndurain played a leading role in the development of High Energy Physics in Spain and all over he was one of the founders of the International Meeting on Fundamental Physics in 1973 (in those days called International Winter Meeting on Fundamental Physics). The efficient assistance of M. Fatas in the organization of the conference is warmly appreciated. We thank R. Pascual for helping us to find the excellent hotel Calipolis where the meeting took place. We are deeply indebted to M. J. Josa and to the HEGRA people form the UCM for their valuable technical assistance along the entire process of preparing the Meeting. We also thank J. C. Gonzalez and M. Lopez for their effort in the preparation of these proceedings and finally to p. Seoane for the design of the poster, advertisements and the logo of the Meeting. Finally

Technical meeting on decommissioning of fast reactors after sodium draining. Working material

International Nuclear Information System (INIS)

2005-01-01

The objective of the technical meeting was to provide a forum for in-depth scientific and technical exchange on topics related to the decommissioning experience with fast reactors, in particular with regard to the decommissioning of components after sodium draining. Accordingly, the scope of the meeting covers the review and analyses of the experience gained from the decommissioning of both active sodium loops and sodium cooled fast reactors (e.g., KNK II, Superphenix, RAPSODIE, EBR-II, FERMI, BN-350, BR-10). It is expected that the outcome of the meeting will contribute to the Agency initiative to preserve fast reactor data and knowledge. The main focus of the technical meeting was given on the decommissioning of both active loop and reactor components (e.g., the primary vessel of a sodium-cooled reactor) that have been drained of sodium, but that still conserve some residual amounts of sodium (e.g., films covering the entire surface of the component, or particular sodium heels that cannot be drained)

The 1996 meeting of the national technical workgroup on mixed waste thermal treatment

International Nuclear Information System (INIS)

1996-01-01

The National Technical Workgroup on Mixed Waste Thermal Treatment held its annual meeting in Atlanta Georgia on March 12-14, 1996. The National Technical Workgroup (NTW) and this meeting were sponsored under an interagency agreement between EPA and DOE. The 1996 Annual Meeting was hosted by US DOE Oak Ridge Operations in conjunction with Lockheed Martin Energy Systems - Center for Waste Management. A new feature of the annual meeting was the Permit Writer Panel Session which provided an opportunity for the state and federal permit writers to discuss issues and potential solutions to permitting mixed waste treatment systems. In addition, there was substantial discussion on the impacts of the Waste Combustion Performance Standards on mixed waste thermal treatment which are expected to proposed very soon. The 1996 meeting also focussed on two draft technical resource documents produced by NTW on Waste Analysis Plans and Compliance Test Procedures. Issues discussed included public involvement, waste characterization, and emission issues

Water Chemistry and Clad Corrosion/Deposition Including Fuel Failures. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-03-01

Corrosion is a principal life limiting degradation mechanism in nuclear steam supply systems, particularly taking into account the trends in increasing fuel burnup, thermal ratings and cycle length. Further, many plants have been operating with varying water chemistry regimes for many years, and issues of crud (deposition of corrosion products on other surfaces in the primary coolant circuit) are of significant concern for operators. At the meeting of the Technical Working Group on Fuel Performance and Technology (TWGFPT) in 2007, it was recommended that a technical meeting be held on the subject of water chemistry and clad corrosion and deposition, including the potential consequences for fuel failures. This proposal was supported by both the Technical Working Group on Advanced Technologies for Light Water Reactors (TWG-LWR) and the Technical Working Group on Advanced Technologies for Heavy Water Reactors (TWG-HWR), with a recommendation to hold the meeting at the National Nuclear Energy Generating Company ENERGOATOM, Ukraine. This technical meeting was part of the IAEA activities on water chemistry, which have included a series of coordinated research projects, the most recent of which, Optimisation of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC) (IAEATECDOC-1666), concluded in 2010. Previous technical meetings were held in Cadarache, France (1985), Portland, Oregon, USA (1989), Rez, Czech Republic (1993), and Hluboka nad Vltavou, Czech Republic (1998). This meeting focused on issues associated with the corrosion of fuel cladding and the deposition of corrosion products from the primary circuit onto the fuel assembly, which can cause overheating and cladding failure or lead to unplanned power shifts due to boron deposition in the clad deposits. Crud deposition on other surfaces increases radiation fields and operator dose and the meeting considered ways to minimize the generation of crud to avoid

Annual technical meeting of the NRC cooperative severe accident research program

International Nuclear Information System (INIS)

Silver, E.G.

1993-01-01

This brief report summarizes the 1992 annual technical meeting of the NRC Cooperative Severe Accident Research Program (CSARP-92) held at the Hyatt Regency Hotel in Bethesda, Maryland, May 4-8, 1992. The report is taken mainly from coverage of the meeting published in the June 5, 1992, issue of Atomic Energy Clearinghouse. Results of this meeting are formalized at the Water Reactor Safety Information Meetings (WRSIM) that are held annually in October. Nuclear Safety summarizes the annual WRSIM meetings and provides a list of the presentations that were given. Interested readers are encouraged to review listed topics to identify specific topic areas in severe accident research. Sessions were held on in-vessel core melt progression; fuel-coolant interactions; fission-product behavior; direct containment heating; and severe accident code development, assessment, and validation. Summaries of the individual technical sessions and the current state of the art in these areas were given by the chairmen

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

International VLBI Service for Geodesy and Astrometry: General Meeting Proceedings

Science.gov (United States)

Vandenberg, Nancy R. (Editor); Baver, Karen D. (Editor)

2002-01-01

This volume contains the proceedings of the second General Meeting of the International VLBI Service for Geodesy and Astrometry (IVS), held in Tsukuba, Japan, February 4-7, 2002. The contents of this volume also appear on the IVS Web site at http://ivscc.gsfc.nasa.gov/publications/gm2002. The key-note of the second GM was prospectives for the future, in keeping with the re-organization of the IAG around the motivation of geodesy as 'an old science with a dynamic future' and noting that providing reference frames for Earth system science that are consistent over decades on the highest accuracy level will provide a challenging role for IVS. The goal of the meeting was to provide an interesting and informative program for a wide cross section of IVS members, including station operators, program managers, and analysts. This volume contains 72 papers and five abstracts of papers presented at the GM. The volume also includes reports about three splinter meetings held in conjunction with the GM: a mini-TOW (Technical Operations Workshop), the third IVS Analysis Workshop and a meeting of the analysis working group on geophysical modeling.

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

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

Energy Technology Data Exchange (ETDEWEB)

Abriola, D.; Tuli, J.

2009-03-23

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

Proceedings of the 18th technical meeting on nuclear reactor and radiation for KURRI engineers and the 9th technical official group section 5 meeting in Kyoto University

International Nuclear Information System (INIS)

2010-03-01

This report is a summary of 18th Technical Meeting on Nuclear Reactor and Radiation for KURRI Engineers in Kyoto University. This was also the 9th meeting for technical official group section 5 (nuclear and radiation) in Kyoto University. In the workshop, three special lectures held were: (1) 'On Border Between Subcritical and Supercritical', (2) 'Memories of Nuclear Power Plant Management for 40 Years', and (3) 'Introduction of Technical Office in Faculty of Engineering, Kyoto University'. The technical presentations held were: (1) 'Radiation Background Study of Specialty Products in Senshu Region', (2) 'Introduction of Radioactivation Analysis at KUR', (3) 'Consideration of Critical Approach Method for KUR Low-Enrichment Fuel Reactor Core Using SRAC', (4) 'Evaluation of Temperature Coefficient of KUR Low-Enrichment Fuel Reactor Core Using SRAC'. As training for technical staffs in Technical Office, we visited the facility in Ashiu Research Forest. An introduction of this facility and the comments from the participants were included in this report. (S.K.)

Seventh ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Raeder, J.; Gordon, C.

2000-01-01

From February 15 to 18, 2000, the Seventy Technical Meeting on Safety and Environment was held at the Garching Joint Work Site which now hosts the Safety, Environment and Health Group of the ITER Joint Central Team. At this meeting, safety experts from the Home Teams worked with the SEHG members on reviews and agreements on the contents of GSSR and on the tasks and the schedule for the production of GSSR as well as the design information to be used and for the analyses to be done

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

International linear collider. A technical progress report

Energy Technology Data Exchange (ETDEWEB)

Arnold, Ned [Argonne National Laboratory, IL (United States); Aderhold, Sebastian [DESY, Hamburg (Germany); Adolphsen, Chris [Stanford Linear Accelerator Center, Menlo Park, CA (United States); and others

2012-07-01

The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R and D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

International Linear Collider-A Technical Progress Report

Energy Technology Data Exchange (ETDEWEB)

Elsen, Eckhard; /DESY; Harrison, Mike; /Brookhaven; Hesla, Leah; /Fermilab; Ross, Marc; /Fermilab; Royole-Degieux, Perrine; /Paris, IN2P3; Takahashi, Rika; /KEK, Tsukuba; Walker, Nicholas; /DESY; Warmbein, Barbara; /DESY; Yamamoto, Akira; /KEK, Tsukuba; Yokoya, Kaoru; /KEK, Tsukuba; Zhang, Min; /Beijing, Inst. High Energy Phys.

2011-11-04

The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R&D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

Mixed Methods in Education Research. IES Technical Working Group Meeting. Meeting Summary (Washington, DC, May 29, 2015)

Science.gov (United States)

Institute of Education Sciences, 2015

2015-01-01

This meeting summary is organized into two major sections. The first section captures the individual contribution of meeting participants, including both Institute of Education Sciences (IES) staff and the invited technical working group members. The second section captures themes that arose during the group discussions, which were organized…

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

International Nuclear Information System (INIS)

1999-11-01

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

Technical meeting on materials for in-vessel components of ITER

International Nuclear Information System (INIS)

Kalinin, G.; Barabash, V.

2000-01-01

The Technical meeting on materials for in-vessel components of ITER was held at the ITER Joint Work Site in Garching from 31 January to 4 February. The main objectives of the meetings were: 1. to summarize the requirements, 2. to review new data, 3. to discuss in detail the R and D program and to discuss the material assessment report

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...

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)

Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

International Nuclear Information System (INIS)

2002-01-01

The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations

Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations.

Meeting of the ITER CTA Project Board

International Nuclear Information System (INIS)

Vlasenkov, V.

2002-01-01

The meeting of the ITER co-ordinated technical activities project board took place in Tokyo, Japan, on 21 January 2002, coinciding with the second Negotiators meeting (N2). Twelve participants, project board members and experts from Canada, European Union, the Russian Federation and the international team attended the meeting. The project board agreed to provide an R and D plan by June 2002, to be linked with the procurement allocation, for the period following the CTA. The ITER International Team Leader developed a proposal on establishing the working groups for drafting technical specifications for the most urgent procurement items

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

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

Sixth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Saji, G.; Baker, D.

1997-01-01

The article summarizes the topics of the Sixth Technical Meeting on Safety and Environment which was held to review the first draft of the Non-Site Specific Safety Report (NSSR-2) and the draft of the ITER Final Design Report Safety Assessment (FDR-Safety) during October 27 - November 4, 1997 at the ITER San Diego Joint Work Site

Data Evaluation for Atomic, Molecular and Plasma Material Interaction Processes in Fusion. Summary Report of a Joint IAEA-NFRI Technical Meeting

International Nuclear Information System (INIS)

Chung, Hyun-Kyung

2012-12-01

This report summarizes the proceedings of the Joint IAEA-NFRI Technical Meeting on 'Data Evaluation for Atomic, Molecular and Plasma Material Interaction Processes in Fusion' on 4-7 September 2012. Twenty five participants from 10 Member States and two from the IAEA attended the four-day meeting held at the Daejeon Convention Center in Daejeon, Republic of Korea hosted by the National Fusion Research Institute (NFRI) in conjunction with the 8th International Symposium on Standard Reference Data. The report includes discussions on the issues of the critical assessment of fundamental data required for fusion and plasma applications, meeting conclusions and recommendations. The abstracts of presentations presented in the meeting are attached in the Appendix. (author)

International technical working group cooperation to counter illicit nuclear trafficking

International Nuclear Information System (INIS)

Smith, D.K.

2004-01-01

Full text: The Nuclear Smuggling International Technical Working Group (ITWG) is an international group of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking. ITWG members include policy and decision makers, law enforcement personnel, and scientists with expertise in, and responsibility for, nuclear forensics. It remains an association of active practitioners of nuclear forensics underwritten by funding from sponsoring countries and organizations. While the primary mission of the ITWG continues to be advancing the science and techniques of nuclear forensics and sharing technical and information resources to combat nuclear trafficking, recently the ITWG has focused on improvements to its organization and outreach. Central is the establishment of guidelines for best practices in nuclear forensics, conducting international exercises, promoting research and development, communicating with external organizations, providing a point-of-contact for nuclear forensics assistance, and providing mutual assistance in nuclear forensics investigations. By its very nature nuclear trafficking is a transboundary problem; nuclear materials

Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (39th annual meeting). Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The 39th Annual Meeting of the Technical Working Group on Fast Reactors (TWG FR) was held from 15-19 May 2006 in Beijing, China, at the invitation of the China Institute of Atomic Energy (CIAEA). The meeting was attended by TWG-FR Members and Advisers from the following Member States (MS): Belgium (observer), Brazil, China, France, Germany, India, Italy, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, Sweden (observer), the United Kingdom, and the United States. Belarus, Switzerland, the European Commission, and OECD/NEA were unable to participate. Moreover, Prof. Carlo Rubbia, CERN director general emeritus, participated, upon IAEA invitation, in the meeting as distinguished scientist and IAEA expert. Mr. S.C. Chetal, from India (Indira Gandhi Centre for Atomic Research, IGCAR), was appointed chairman. The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 38th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2006 and 2007; - Reviewed the Agency's ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as co-ordination of the TWG-FR's activities with other organizations; - Discuss future joint activities in view of the Agency's Programme and Budget Cycle 2008-2009 (and beyond)

Model for prioritization of regional strategies within the technical cooperation of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Silva, Pedro Maffia da

2017-01-01

The International Atomic Energy Agency's Technical Cooperation Program is the main mechanism through which services are provided to its member states to help them build, strengthen and maintain their capabilities in the safe use of nuclear technology in support of socio-economic development. The technical cooperation program operates in four geographical regions, each regional program helps Member States to meet their specific needs, taking into account existing capacities and different operating conditions. The technical cooperation regions are Asia and the Pacific, Europe, Africa and Latin America and the Caribbean. Developing activities together with the technical cooperation program we have the Regional Cooperation Agreement for the Promotion of Nuclear Science and Technology in Latin America and the Caribbean (ARCAL), which involves the majority of the members of the International Atomic Energy Agency of that region, for Technical Cooperation. All ARCAL's work is guided by the Regional Strategic Profile, which identifies the needs and problems of the region that require support projects. In the technical meeting of the Regional Strategic Profile, the needs and problems that are analyzed through indexes associated with severity, urgency, extension, relevance and difficulty are listed by different thematic areas. To these indexes, values are established by the technical staff on a continuous scale between 1 and 5. From these values an expression is used to arrive at a priority number for the needs and problems. In the face of many criticisms associated with similar approaches, such as Failure Modes and Effects Analysis, and Timing, Trend and Impact Matrix, the aim of this thesis is to propose a methodological approach that can assist in the prioritization of investments of technical cooperation projects and programs that take into account the budget available and the technical and strategic visions of the parties involved. For this, the Probabilistic Composition

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

International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 2

International Nuclear Information System (INIS)

1995-01-01

This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 1

International Nuclear Information System (INIS)

1995-01-01

This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

Scientific Meetings Database: A New Tool for CTBT-Related International Cooperation

Energy Technology Data Exchange (ETDEWEB)

Knapik, Jerzy F.; Girven, Mary L.

1999-08-20

The mission of international cooperation is defined in the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Ways and means of implementation were the subject of discussion during the International Cooperation Workshop held in Vienna in November 1998, and during the Regional Workshop for CTBTO International Cooperation held in Cairo, Egypt in June 1999. In particular, a database of ''Scientific and Technical Meetings Directly or Indirectly Related to CTBT Verification-Related Technologies'' was developed by the CTBTO PrepCom/PTS/International Cooperation section and integrated into the organization's various web sites in cooperation with the U.S. Department of Energy CTBT Research and Development Program. This database, the structure and use of which is described in this paper/presentation is meant to assist the CTBT-related scientific community in identifying worldwide expertise in the CTBT verification-related technologies and should help experts, particularly those of less technologically advanced States Signatories, to strengthen contacts and to pursue international cooperation under the Tredy regime. Specific opportunities for international cooperation, in particular those provided by active participation in the use and further development of this database, are presented in this paper and/or presentation.

Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-07-01

This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

International Experts' Meeting on Decommissioning and Remediation after a Nuclear Accident. Presentations

International Nuclear Information System (INIS)

2013-01-01

Against the backdrop of the accident at TEPCO's Fukushima Daiichi nuclear power plant in March 2011, the Director General of the International Atomic Energy Agency (IAEA) convened the IAEA Ministerial Conference on Nuclear Safety in Vienna, Austria, in June 2011. The Conference adopted a Ministerial Declaration which, inter alia, requested the Director General to prepare a draft Action Plan covering all the relevant aspects relating to nuclear safety, emergency preparedness and response, and radiation protection of people and the environment, as well as the relevant international legal framework. On 22 September 2011, the IAEA General Conference unanimously endorsed the draft IAEA Action Plan on Nuclear Safety approved by the Board of Governors. The Action Plan sets out a comprehensive programme of work, in 12 major areas, to strengthen nuclear safety worldwide. Under one of these areas, headed 'Enhance transparency and effectiveness of communication and improve dissemination of information', the IAEA Secretariat was requested to organize an International Experts' Meeting (IEM) on decommissioning, cleanup and remediation of nuclear facilities and contaminated lands after a nuclear accident. This IEM was organized in response to that request. The IEM focussed on the complex technical, societal, environmental and economic issues that need to be considered for decommissioning and remediation activities after a nuclear accident, specifically after the emergency exposure situation of an accident has been declared ended. The objective of the IEM is to assist Member States to prepare for and to be able to manage the consequences resulting from a nuclear accident. The meeting highlighted the specific short term and long term issues that may need to be addressed during decommissioning of facilities and remediation of the off-site environment affected by a nuclear accident. It is of interest to a wide range of experts, such as decision makers, regulators, operators

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

International Nuclear Information System (INIS)

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

2007-09-01

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

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.

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...

Technical meeting on lessons learned with respect to SAT implementation, including development of trainers and use of cost effective training methods

International Nuclear Information System (INIS)

2002-01-01

The past years have brought some significant changes in the world energy market, where the nuclear power plants and utilities are operating. Part of NPPs is privatised now; the electricity markets are liberalized and become more and more international. Due to the increase of competition, the power production costs are now monitored more closely than before. The opening of electricity markets has led the nuclear power plants to be under the serious economic pressure with a demand for continuous cost reduction. All these require from NPPs to make their personnel training more cost-effective. In addition, based on modern technology, a great amount of new training tools, aids and technologies have been introduced during the last 2-3 years, these new opportunities can be quite useful for training cost optimization. On the basis of experience gained worldwide in the application of the systematic approach to training (SAT), SAT based training is now a broad integrated approach emphasizing not only technical knowledge and skills but also human factor related knowledge, skills and attitudes. In this way, all competency requirements for attaining and maintaining personnel competence and qualification can be met, thus promoting and strengthening quality culture and safety culture, which should be fostered throughout the initial and continuing training programmes. The subject of the present technical meeting was suggested by the members of the Technical Working Group on Training and Qualification of NPP Personnel (TWG-T and Q) and supported by a number of the IAEA meetings on NPP personnel training. The technical Meeting on 'Lessons Learned with Respect to SAT Implementation, Including Development of Trainers and Use of Cost Effective Training Methods' was organized by the IAEA in co-operation with the Tecnatom A.S. and was held from 21 to 24 October 2002 in San Sebastian de los Reyes/ Madrid, Spain. The main objective of the meeting was to provide an international forum for

Nineteenth International Microgravity Measurements Group Meeting

Science.gov (United States)

DeLombard, Richard (Compiler)

2000-01-01

The Microgravity Measurements Group meetings provide a forum for an exchange of information and ideas about various aspects of microgravity acceleration research in international microgravity research programs. These meetings are sponsored by the PI Microgravity Services (PIMS) project at the NASA Glenn Research Center. The 19th MGMG meeting was held 11-13 July 2000 at the Sheraton Airport Hotel in Cleveland, Ohio. The 44 attendees represented NASA, other space agencies, universities, and commercial companies; 8 of the attendees were international representatives from Japan, Italy, Canada, Russia, and Germany. Twenty-seven presentations were made on a variety of microgravity environment topics including the International Space Station (ISS), acceleration measurement and analysis results, science effects from microgravity accelerations, vibration isolation, free flyer satellites, ground testing, vehicle characterization, and microgravity outreach and education. The meeting participants also toured three microgravity-related facilities at the NASA Glenn Research Center. Contained within the minutes is the conference agenda, which indicates each speaker, the title of their presentation, and the actual time of their presentation. The minutes also include the charts for each presentation, which indicate the authors' name(s) and affiliation. In some cases, a separate written report was submitted and has been Included here

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

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...

Proceedings of the meeting on the technical study at KEK

Energy Technology Data Exchange (ETDEWEB)

Honma, H.; Tokumoto, S.; Kosuge, T. [National Lab. for High Energy Physics, Tsukuba, Ibaraki (Japan)] [eds.

1996-03-01

This report is a summary report of lectures carried out at the technical meeting on ``control technique of network sequencer application and others`` held by the Technical Information and Library, National Laboratory for High Energy Physics, on November 28th and 29th, 1995. In this meeting, 10 lectures are reported to introduce the control technique in each study field for proposing each common topic subject. They are present status of PS accelerator control, improvement of positron accelerator control system, device controller due to sequencer, data acquisitting (DAQ) system using VMEbus, monitoring and controlling system using sequencer at counter hole, radiation beam line interlock system and network, control of superconducting wiggler through network using Visual Basic, microwave monitoring system for KEKB, data transmission of monitor, and development of machining equipment of mirror for X-ray collecting. (G.K.)

NASA Technical Interchange Meeting (TIM): Advanced Technology Lifecycle Analysis System (ATLAS) Technology Tool Box

Science.gov (United States)

ONeil, D. A.; Craig, D. A.; Christensen, C. B.; Gresham, E. C.

2005-01-01

The objective of this Technical Interchange Meeting was to increase the quantity and quality of technical, cost, and programmatic data used to model the impact of investing in different technologies. The focus of this meeting was the Technology Tool Box (TTB), a database of performance, operations, and programmatic parameters provided by technologists and used by systems engineers. The TTB is the data repository used by a system of models known as the Advanced Technology Lifecycle Analysis System (ATLAS). This report describes the result of the November meeting, and also provides background information on ATLAS and the TTB.

Proceedings of neutron irradiation technical meeting on BNCT

International Nuclear Information System (INIS)

2000-10-01

The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

Internal contamination: what challenges for tomorrow? Proceedings of the Research and Health Section technical day

International Nuclear Information System (INIS)

Berard, Philippe; Lecoix, Geraldine; Menetrier, Florence; Menetrier, Florence; Leiterer, Alexandra; Gremy, Olivier; Mougnard, Philippe; Gonin, Michele; Paquet, Francois; Davesne, Estelle; Bertho, Jean-Marc; Metivier, Henri; Abergel, Rebecca

2015-10-01

The Research and Health Section of the French Society of Radiation Protection (SFRP) organized a technical meeting on the radiation protection aspects of dismantlement, from the dismantling work to the risk, the measurement of body contamination, the potentially harmful health effects, the available medical treatments, the actual needs and the developments in progress. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Situation: what radionuclides, what situations? (Philippe BERARD, CEA); 2 - Dismantling workplace experience feedback with internal contamination hazard (Philippe MOUGNARD, AREVA); 3 - Experience feedback on internal exposure monitoring at power plants in France (Michele GONIN, EDF); 4 - Evolution of routine and intervention measurement methods (Geraldine LECOIX, CEA); 5 - Evolution of radiation dose calculation models (Francois PAQUET, IRSN); 6 - Taking uncertainties into account in internal contamination monitoring protocols (Estelle DAVESNE, IRSN); 7 - Radionuclides behaviour and effects in men (Florence MENETRIER, CEA); 8 - The plutonium case (Henri METIVIER, SFRP); 9 - Cesium-137 and internal contamination: status and perspectives (Jean-Marc BERTHO, IRSN); 10 - Iodine and thyroid (Florence MENETRIER, CEA); 11 - Actual treatments and research pathways (Alexandra LEITERER, CEA); 12 - Radionuclide contamination treatment: new developments in the US (Rebecca ABERGEL, Berkeley USA); 13 - Internal contaminations treatment: French recent effort for its improvement (Olivier GREMY, CEA)

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...

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

International Nuclear Information System (INIS)

Abriola, D.; Tuli, J.K.

2009-10-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2005-09-15

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

Third ITER International Industry Liaison Meeting

International Nuclear Information System (INIS)

Dautovich, D.

2000-01-01

Following previous meetings held in 1996 in San Diego and in 1997 in Tokyo, the Third ITER International Industry Liaison Meeting (IILM) meeting was held under the European Chairmanship in Toronto, Canada, November 7-9, 2000. The intention of such meetings is to provide a forum for industrialists of the ITER EDA parties and other interested countries to develop common understandings on important issues of the timing and nature of Industry involvement in the ITER project. This article describes the main views from Industry on the preconstruction and construction phases and the cost and benefit schemes, while summarizing the progress made by the ITER project since the Tokyo meeting

Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2012-01-01

The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.). The 45th Meeting of the TWG-FR reached the following conclusions/recommendations: • The participants expressed satisfaction and appreciation for the large amount of new information on on-going activities carried out by the Member States in the field of FR and ADS exchanged during the meeting; • Also the organizations which have participated to the TWG-FR meeting for the first time expressed their appreciation for the lively discussion and the results and thanked the IAEA for inviting them at the meeting; • The meeting was very useful in particular for collecting inputs and advice in view of the preparation of the IAEA Programme & Budget 2014-2015 (and then 2016-2017) in the area of FR and ADS technology development; • The TWG-FR remains an unique international forum for information exchange in the field of fast neutron systems and for promoting RT&D activities in this area; • Due to the increasing interest in FR and in view of the forthcoming realizations, it would be advisable to increase the involvement of industries, regulators and other R&D organizations; • The annual TWG-FR meeting should focused on exchange of information on national and international programmes, avoiding duplications or overlapping’s with other IAEA initiatives in the field; �

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

Energy Technology Data Exchange (ETDEWEB)

Travelli, A [Argonne National Laboratory, Argonne, IL (United States)

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

International Nuclear Information System (INIS)

Travelli, A.

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Report of a Technical Meeting on ''Alpha emitting radionuclides and radiopharmaceuticals for therapy''

International Nuclear Information System (INIS)

2013-01-01

Considering the high potential of α-emitters for future development of radionuclide therapy, the International Atomic Energy Agency (IAEA) organized a Technical Meeting on ‘Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy’, from June 24 to 28, 2013, at IAEA Headquarters in Vienna with the purpose of gathering eminent Experts in the field and discuss with them the status and future perspectives of the field. Sixteen Experts and two External Observers from ten different countries, and four IAEA Technical Officers attended this meeting. Outstanding lectures have been presented covering all relevant aspects of α-therapy, which were followed by extensive discussions and analysis. Selected arguments encompassed production methods and availability of alpha-emitting radionuclides, labelling chemistry of alpha-emittting radioelements, design and development of target-specific radiopharmaceuticals, physical principles of alpha-particle dosimetry and advanced dosimetric models, biological effects of alpha radiation at the cellular level, on-going preclinical and clinical studies with new radiopharmaceuticals, results of clinical trials on the use of radium-223 chloride solutions for the treatment of metastatic bone cancer. The broad scientific background of invited components of the Experts’ panel conferred a strong interdisciplinary trait to the overall discussion and stimulated a critical analysis of this emerging unexplored field. Results of this comprehensive overview on alpha therapy, including recommendations to the Agency on suitable initiatives that may help to promote and spread the knowledge to Members States on this emerging therapeutic modality, are summarized in the present Report

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

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

Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-04-01

Fast reactors are vital for ensuring the sustainability of nuclear energy in the long term. They offer vastly more efficient use of uranium resources and the ability to burn actinides, which are otherwise the long-lived component of high level nuclear waste. These reactors require development, qualification, testing and deployment of improved and innovative nuclear fuel and structural materials having very high radiation resistance, corrosion/erosion and other key operational properties. Several IAEA Member States have made efforts to advance the design and manufacture of technologies of fast reactor fuels, as well as to investigate their irradiation behaviour. Due to the acute shortage of fast neutron testing and post-irradiation examination facilities and the insufficient understanding of high dose radiation effects, there is a need for international exchange of knowledge and experience, generation of currently missing basic data, identification of relevant mechanisms of materials degradation and development of appropriate models. Considering the important role of nuclear fuels in fast reactor operation, the IAEA Technical Working Group on Fuel Performance and Technology (TWGFPT) proposed a Technical Meeting (TM) on 'Design, Manufacturing and Irradiation Behaviour of Fast Reactors Fuels', which was hosted by the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russian Federation, from 30 May to 3 June 2011. The TM included a technical visit to the fuel production plant MSZ in Elektrostal. The purpose of the meeting was to provide a forum to share knowledge, practical experience and information on the improvement and innovation of fuels for fast reactors through scientific presentations and brainstorming discussions. The meeting brought together 34 specialists from national nuclear agencies, R and D and design institutes, fuel vendors and utilities from 10 countries. The presentations were structured into four sections: R and D Programmes on FR Fuel

Proceedings of neutron irradiation technical meeting on BNCT

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-10-01

The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

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.

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

Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting

Energy Technology Data Exchange (ETDEWEB)

Gephart, J.M. [ed.

1997-05-01

This document contains summaries of technology development presented at the 1997 Efficient Separations and Processing Crosscutting Program (ESP-CP) Technical Exchange Meeting (TEM), held January 28-30, 1997, in Gaithersburg, Maryland. The ESP-CP is sponsored by the U.S. Department of Energy`s Office of Environmental Management (DOE/EM), Office of Science and Technology. The ESP-CP TEM is held annually to: (1) Present current technology development activities funded by the ESP-CP. Developers of ESP-CP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Representatives from DOE/EM`s Focus Areas also present their technology needs. (2) Promote the exchange of technical information among those developing new separations technologies, those responsible for providing new separations technologies to meet DOE/EM needs, and those who need or will potentially make use of such technologies. (3) Familiarize the ESP-CP Technical Review Team with the FY 1997 program and solicit reviewers` views on the program as a whole. This meeting is not a program review of the individual tasks, but instead focuses on the technical aspects and implementation of ESP-CP-sponsored technology or data. This document also contains a list of ESP-CP-sponsored publications, presentations, and patents. Separate abstracts have been indexed into the energy database for contributions to this proceedings.

Proceedings of the efficient separations and processing crosscutting program 1997 technical exchange meeting

International Nuclear Information System (INIS)

Gephart, J.M.

1997-01-01

This document contains summaries of technology development presented at the 1997 Efficient Separations and Processing Crosscutting Program (ESP-CP) Technical Exchange Meeting (TEM), held January 28-30, 1997, in Gaithersburg, Maryland. The ESP-CP is sponsored by the U.S. Department of Energy's Office of Environmental Management (DOE/EM), Office of Science and Technology. The ESP-CP TEM is held annually to: (1) Present current technology development activities funded by the ESP-CP. Developers of ESP-CP-funded technologies describe the problems and needs addressed by their technologies; the technical approach, accomplishments, and resolution of issues; the strategy and schedule for commercialization; and evolving potential applications. Representatives from DOE/EM's Focus Areas also present their technology needs. (2) Promote the exchange of technical information among those developing new separations technologies, those responsible for providing new separations technologies to meet DOE/EM needs, and those who need or will potentially make use of such technologies. (3) Familiarize the ESP-CP Technical Review Team with the FY 1997 program and solicit reviewers' views on the program as a whole. This meeting is not a program review of the individual tasks, but instead focuses on the technical aspects and implementation of ESP-CP-sponsored technology or data. This document also contains a list of ESP-CP-sponsored publications, presentations, and patents. Separate abstracts have been indexed into the energy database for contributions to this proceedings

Summary report of technical meeting on neutron cross section covariances

International Nuclear Information System (INIS)

Trkov, A.; Smith, D.L.; Capote Noy, R.

2011-01-01

A summary is given of the Technical Meeting on Neutron Cross Section Covariances. The meeting goal was to assess covariance data needs and recommend appropriate methodologies to address those needs. Discussions on covariance data focused on three general topics: 1) Resonance and unresolved resonance regions; 2) Fast neutron region; and 3) Users' perspective: benchmarks' uncertainty and reactor dosimetry. A number of recommendations for further work were generated and the important work that remains to be done in the field of covariances was identified. (author)

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...

Proceedings of the technical exchange meeting on passive radon monnitoring

Energy Technology Data Exchange (ETDEWEB)

Duray, J.R.; Langner, H. Jr.; Martz, D.E.

1987-09-01

The purpose of the meeting was to bring together a number of scientists active in the development and use of passive radon monitoring instrumentation, primarily activated charcoal detectors and alpha track detectors. Many of those present expressed a desire to receive copies of the viewgraphs and other materials presented. Most have supplied extended abstracts or complete reports. These materials are reproduced here as a Technical Measurements Center Report for the benefit of those attending the meeting and for others interested in passive radon monitoring. Individual papers were processed separately for the data base.

Proceedings of the technical exchange meeting on passive radon monnitoring

International Nuclear Information System (INIS)

Duray, J.R.; Langner, H. Jr.; Martz, D.E.

1987-09-01

The purpose of the meeting was to bring together a number of scientists active in the development and use of passive radon monitoring instrumentation, primarily activated charcoal detectors and alpha track detectors. Many of those present expressed a desire to receive copies of the viewgraphs and other materials presented. Most have supplied extended abstracts or complete reports. These materials are reproduced here as a Technical Measurements Center Report for the benefit of those attending the meeting and for others interested in passive radon monitoring. Individual papers were processed separately for the data base

Funding for the 2ND IAEA technical meeting on fusion data processing, validation and analysis

Energy Technology Data Exchange (ETDEWEB)

Greenwald, Martin

2017-06-02

The International Atomic Energy Agency (IAEA) will organize the second Technical Meeting on Fusion Da Processing, Validation and Analysis from 30 May to 02 June, 2017, in Cambridge, MA USA. The meeting w be hosted by the MIT Plasma Science and Fusion Center (PSFC). The objective of the meeting is to provide a platform where a set of topics relevant to fusion data processing, validation and analysis are discussed with the view of extrapolation needs to next step fusion devices such as ITER. The validation and analysis of experimental data obtained from diagnostics used to characterize fusion plasmas are crucial for a knowledge based understanding of the physical processes governing the dynamics of these plasmas. The meeting will aim at fostering, in particular, discussions of research and development results that set out or underline trends observed in the current major fusion confinement devices. General information on the IAEA, including its mission and organization, can be found at the IAEA websit Uncertainty quantification (UQ) Model selection, validation, and verification (V&V) Probability theory and statistical analysis Inverse problems & equilibrium reconstru ction Integrated data analysis Real time data analysis Machine learning Signal/image proc essing & pattern recognition Experimental design and synthetic diagnostics Data management

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

International Nuclear Information System (INIS)

2000-01-01

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

12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems

Energy Technology Data Exchange (ETDEWEB)

Berk, Herbert L.; Breizman, Boris N.

2014-02-21

The 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems took place in Austin, Texas (7–11 September 2011). This meeting was organized jointly with the 5th IAEA Technical Meeting on Theory of Plasma Instabilities (5–7 September 2011). The two meetings shared one day (7 September 2011) with presentations relevant to both groups. Some of the work reported at these meetings was then published in a special issue of Nuclear Fusion [Nucl. Fusion 52 (2012)]. Summaries of the Energetic Particle Conference presentations were given by Kazuo Toi and Boris Breizman. They respectively discussed the experimental and theoretical progress presented at the meeting. Highlights of this meeting include the tremendous progress that has been achieved in the development of diagnostics that enables the ‘viewing’ of internal fluctuations and allows comparison with theoretical predictions, as demonstrated, for example, in the talks of P. Lauber and M. Osakabe. The need and development of hardened diagnostics in the severe radiation environment, such as those that will exist in ITER, was discussed in the talks of V. Kiptily and V.A. Kazakhov. In theoretical studies, much of the effort is focused on nonlinear phenomena. For example, detailed comparison of theory and experiment on D-III-D on the n = 0 geodesic mode was reported in separate papers by R. Nazikian and G. Fu. A large number of theoretical papers were presented on wave chirping including a paper by B.N. Breizman, which notes that wave chirping from a single frequency may emanate continuously once marginal stability conditions have been established. Another area of wide interest was the detailed study of alpha orbits in a burning plasma, where losses can come from symmetry breaking due to finite coil number or magnetic field imperfections introduced by diagnostic or test modules. An important area of development, covered by M.A. Hole and D.A. Spong, is concerned with the self

Scientific meetings

International Nuclear Information System (INIS)

1973-01-01

One of the main aims of the IAEA is to foster the exchange of scientific and technical information and one of the main ways of doing this is to convene international scientific meetings. They range from large international conferences bringing together several hundred scientists, smaller symposia attended by an average of 150 to 250 participants and seminars designed to instruct rather than inform, to smaller panels and study groups of 10 to 30 experts brought together to advise on a particular programme or to develop a set of regulations. The topics of these meetings cover every part of the Agency's activities and form a backbone of many of its programmes. (author)

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

Regional dimensions of international scientific and technical cooperation

Directory of Open Access Journals (Sweden)

Tetiana Chernytska

2013-02-01

Full Text Available The article has examined a phenomenon of international scientific and technical cooperation within individual regions, conditions and factors of its formation. It has been analyzed the evolution, basic essential features, models and trends of development of local innovation alliances, their participation in international scientific and technical cooperation. It has been proposed the priorities of formation of a quality mechanism to improve this form of cooperation in Ukraine and establishment of prerequisites for its expansion with European organizational structures that operate in innovation field (technology parks, technology clusters, innovation centers, etc..

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-10-15

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

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

International Nuclear Information System (INIS)

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

2011-10-01

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

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

Third International Meeting on Next Generation Safeguards: Safeguards-by-Design at Enrichment Facilities

International Nuclear Information System (INIS)

Long, Jon D.; McGinnis, Brent R.; Morgan, James B.; Whitaker, Michael; Lockwood, Dunbar; Shipwash, Jacqueline L.

2011-01-01

The Third International Meeting on Next Generation Safeguards (NGS3) was hosted by the U.S. Department of Energy (DOE)/National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) in Washington, D.C. on 14-15 December 2010; this meeting focused on the Safeguards-by-Design (SBD) concept. There were approximately 100 participants from 13 countries, comprised of safeguards policy and technical experts from government and industry. Representatives also were present from the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), the European Atomic Energy Agency (Euratom), and the International Atomic Energy Agency (IAEA). The primary objective of this meeting was to exchange views and provide recommendations on implementation of the SBD concept for four specific nuclear fuel cycle facility types: gas centrifuge enrichment plants (GCEPs), GEN III and GEN IV reactors, aqueous reprocessing plants, and mixed oxide fuel fabrication facilities. The general and facility-specific SBD documents generated from the four working groups, which were circulated for comment among working group participants, are intended to provide a substantive contribution to the IAEA's efforts to publish SBD guidance for these specific types of nuclear facilities in the near future. The IAEA has described the SBD concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' As part of the Next Generation Safeguards Initiative (NGSI), the DOE is working to establish SBD as a global norm through DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its use in new nuclear facilities in the United States. This paper describes the discussion topics and final recommendations of the Enrichment Facilities Working

Report on the consultants` meeting on co-ordination of the nuclear reaction data centers (technical aspects)

Energy Technology Data Exchange (ETDEWEB)

Schwerer, O; Wienke, H [eds.

1997-10-01

The report summarizes the co-ordination meeting of the network of Nuclear Reaction Data Centres organized by the IAEA in 1997. The meeting was attended by technical staff from ten member centres of the network (representing USA, Russia, China, Japan, Hungary, OECD-NEA and IAEA) to discuss technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Observers from Belgium and Ukraine also attended the meeting. The document includes status reports of all centres and selected working papers. Refs, figs, tabs.

Report on the consultants' meeting on co-ordination of the nuclear reaction data centers (technical aspects)

International Nuclear Information System (INIS)

Schwerer, O.; Wienke, H.

1997-10-01

The report summarizes the co-ordination meeting of the network of Nuclear Reaction Data Centres organized by the IAEA in 1997. The meeting was attended by technical staff from ten member centres of the network (representing USA, Russia, China, Japan, Hungary, OECD-NEA and IAEA) to discuss technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Observers from Belgium and Ukraine also attended the meeting. The document includes status reports of all centres and selected working papers

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

International Nuclear Information System (INIS)

2012-01-01

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

Efficient separations and processing crosscutting program 1996 technical exchange meeting. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

This document contains summaries of technology development presented at the 1996 Efficient Separations and Processing Crosscutting Program Technical Exchange Meeting. This meeting is held annually to promote a free exchange of ideas among technology developers, potential users and other interested parties within the EM community. During this meeting the following many separation processes technologies were discussed such as ion exchange, membrane separation, vacuum distillation, selective sorption, and solvent extraction. Other topics discussed include: waste forms; testing or inorganic sorbents for radionuclide and heavy metal removal; selective crystallization; and electrochemical treatment of liquid wastes. This is the leading abstract, individual papers have been indexed separately for the databases.

Efficient separations and processing crosscutting program 1996 technical exchange meeting. Proceedings

International Nuclear Information System (INIS)

1996-01-01

This document contains summaries of technology development presented at the 1996 Efficient Separations and Processing Crosscutting Program Technical Exchange Meeting. This meeting is held annually to promote a free exchange of ideas among technology developers, potential users and other interested parties within the EM community. During this meeting the following many separation processes technologies were discussed such as ion exchange, membrane separation, vacuum distillation, selective sorption, and solvent extraction. Other topics discussed include: waste forms; testing or inorganic sorbents for radionuclide and heavy metal removal; selective crystallization; and electrochemical treatment of liquid wastes. This is the leading abstract, individual papers have been indexed separately for the databases

Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors. Working Material

International Nuclear Information System (INIS)

2015-01-01

A major focus of the design of modern fast reactor systems is on inherent and passive safety. Specific systems to improve reactor safety performance during accidental transients have been developed in nearly all fast reactor programs, and a large number of proposed systems have reached various stages of maturity. This Technical Meeting on Passive Shutdown Systems for Fast Reactors, which was recommended by the Technical Working Group on Fast Reactors (TWG-FR), addressed Member States’ expressed need for information exchange on projects and programs in the field, as well as for the identification of priorities based on the analysis of technology gaps to be covered through R&D activities. This meeting was limited to shutdown systems only, and did not include other passive features such as natural circulation decay heat removal systems etc.; however the meeting catered to passive shutdown safety devices applicable to all types of fast neutron systems. It was agreed to initiate a new study and produce a Nuclear Energy Series (NES) Technical Report to collect information about the existing operational systems as well as innovative concepts under development. This will be a useful source for member states interested in gaining technical expertise to develop passive shutdown systems as well as to highlight the importance and development in this area

Technical minutes of the ninth INDC meeting. Vienna, 16-20 May 1977

International Nuclear Information System (INIS)

Motz, H.

1978-05-01

Progress reports from data centres on data measurements, facilities and evaluations, on coordinating activities are presented along with reports of technical, ad-hoc and policy subcommittees, on plans for cooperation and past meetings

4th IEA International CCS Regulatory Network Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-01

On 9 and 10 May 2012, the IEA International CCS Regulatory Network (Network), launched in Paris in May 2008 to provide a neutral forum for CCS regulators, policy makers and stakeholders to share updates and views on CCS regulatory developments, held its fourth meeting at the International Energy Agency (IEA) offices in Paris, France. The aim of the meeting was to: provide an update on government efforts to develop and implement carbon capture and storage (CCS) legal and regulatory frameworks; and consider ways in which governments are dealing with some of the more difficult or complex aspects of CCS regulation. This report summarises the proceedings of the meeting.

76 FR 69714 - International Energy Agency Meetings

Science.gov (United States)

2011-11-09

...: Notice of Meetings. SUMMARY: The Industry Advisory Board (IAB) to the International Energy Agency (IEA... Industry Advisory Board (IAB) to the International Energy Agency (IEA) will be held at the headquarters of... of Switzerland --Questionnaire Response of The Netherlands 5. Emergency Response Exercises...

International co-operation through scientific and technical nuclear societies

International Nuclear Information System (INIS)

Manning Muntzing, L.

1983-01-01

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

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

77 FR 41203 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2012-07-12

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-057] NASA International Space Station Advisory Committee; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of..., the National Aeronautics and Space Administration announces an open meeting of the NASA International...

78 FR 77502 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2013-12-23

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-154)] NASA International Space Station Advisory Committee; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of..., the National Aeronautics and Space Administration announces a meeting of the NASA International Space...

77 FR 2765 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2012-01-19

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (12-003)] NASA International Space Station Advisory Committee; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of..., the National Aeronautics and Space Administration announces an open meeting of the NASA International...

77 FR 66082 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2012-11-01

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 12-090] NASA International Space Station Advisory Committee; Meeting AGENCY: National Aeronautics and Space Administration (NASA). ACTION: Notice of..., the National Aeronautics and Space Administration announces an open meeting of the NASA International...

IAEA advisory group meeting on technical aspects of atomic and molecular data processing and exchange (16. meeting of the A+M Data Centres and ALADDIN network). Summary report

Energy Technology Data Exchange (ETDEWEB)

Stephens, J A [ed.

2001-12-01

The proceedings of the IAEA Advisory group meeting on technical aspects of atomic and molecular data processing and exchange (16. meeting of A+M Data centers and ALADDIN Network), held on September 10-11, 2001 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange and distribution are also presented. (author)

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

International Nuclear Information System (INIS)

2004-01-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information.

Report on the Technical Meeting on Therapeutic Radiopharmaceuticals

International Nuclear Information System (INIS)

2009-01-01

The purpose of the TM was to provide an experts' platform to facilitate exploring the current status and future directions on therapeutic radiopharmaceuticals. The invited talks and presentations in the TM were in the following topics: - Radionuclide Production; - Production and availability of alpha emitters and their radiopharmaceuticals; - Therapeutic radiopharmaceutical chemistry; - Targets and biological evaluation; - Medical physics and dosimetry; - Clinical applications including radioimmunotherapy and clinical needs; - Peptide receptor mediated therapy Panel discussions: - Radionuclide therapy using alpha emitters; - Regulatory challenges with therapeutic radiopharmaceuticals; - International activities in radionuclide therapy. he technical meeting generated a large interest among scientists and physicians working in the field of targeted therapy using radiopharmaceuticals. Participants from both developed and developing MS reported on recent developments on the research work and clinical studies going on in the field and provided their views on the future developments in this field. The unexpected high number of participants and the high number of presentations with exceptional quality underlines the great interest of scientists and professionals in therapeutic applications using radiolabelled drugs / biomolecules. The intensive discussions including panels specified the challenges in the future on developing novel agents and to finally use them for the benefit of patients. The IAEA can play as vital role in streamlining developments and to provide tools to overcome scientific, professional and regulatory challenges in the field of therapeutic radiopharmaceuticals

Report on the Technical Meeting on Therapeutic Radiopharmaceuticals

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

The purpose of the TM was to provide an experts' platform to facilitate exploring the current status and future directions on therapeutic radiopharmaceuticals. The invited talks and presentations in the TM were in the following topics: - Radionuclide Production; - Production and availability of alpha emitters and their radiopharmaceuticals; - Therapeutic radiopharmaceutical chemistry; - Targets and biological evaluation; - Medical physics and dosimetry; - Clinical applications including radioimmunotherapy and clinical needs; - Peptide receptor mediated therapy Panel discussions: - Radionuclide therapy using alpha emitters; - Regulatory challenges with therapeutic radiopharmaceuticals; - International activities in radionuclide therapy. he technical meeting generated a large interest among scientists and physicians working in the field of targeted therapy using radiopharmaceuticals. Participants from both developed and developing MS reported on recent developments on the research work and clinical studies going on in the field and provided their views on the future developments in this field. The unexpected high number of participants and the high number of presentations with exceptional quality underlines the great interest of scientists and professionals in therapeutic applications using radiolabelled drugs / biomolecules. The intensive discussions including panels specified the challenges in the future on developing novel agents and to finally use them for the benefit of patients. The IAEA can play as vital role in streamlining developments and to provide tools to overcome scientific, professional and regulatory challenges in the field of therapeutic radiopharmaceuticals

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

IAEA advisory group meeting on technical aspects of atomic and molecular data processing and exchange (15. meeting of the A+M data centres and ALADDIN network). Summary report

International Nuclear Information System (INIS)

Stephens, J.A.

1999-12-01

The proceedings of the IAEA Advisory Group Meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (15th Meeting of A+M Data Centres and ALADDIN Network), held on September 13-14, 1999 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A+M data compilation and evaluation, and on the technical aspects of data processing, exchange, and distribution are also presented. (author)

Informing the public on technical effectiveness of international safeguards

International Nuclear Information System (INIS)

Hunt, H.M.

1994-01-01

In recent years, public interest regarding IAEA (International Atomic Energy Agency) safeguards effectiveness has partially shifted to detection of undeclared nuclear facilities. Nevertheless, important segments of the public remain vitally interested in whether international safeguards would be able to reliably and definitively detect diversion of bomb quantities of plutonium or highly enriched uranium from open-quotes bulk handlingclose quotes facilities. There now exists a sizable body of unclassified technical reports, based on experimental results over many years, written by various experts, describing actual capabilities and limitations of safeguards techniques and systems, which collectively lead to definitive evaluations of technical safeguards effectiveness. For a large-scale operation of spent fuel reprocessing, plutonium fuel fabrication, or gas centrifuge uranium enrichment, an undisputable conclusion is that international safeguards systems would be unable to reliably and definitively detect the diversion in a one-year period of a significant quantity of plutonium or enriched uranium; moreover, diversion of many significant quantities per year (from such an operation) would have negligible probability of definitive detection if conducted in accordance with particle diversion scenarios. To properly inform the public and government agencies, reports on technical effectiveness of international safeguards should incorporate these basic conclusions

Policy and technical issues for international safeguards in nuclear weapons states

International Nuclear Information System (INIS)

Markin, J.T.; Stanbro, W.D.

1994-01-01

Expansion of international safeguards into the military and commercial fuel cycles of the nuclear weapons states (NWS) -- the subject of previous proposals in international safeguards discussions and of studies in the safeguards literature -- has been given impetus by recent US government initiatives for safeguards on excess weapons materials and a verified fissile materials production cutoff. These proposals, if implemented, would have implications on the safeguards objectives, approaches, and technologies that are traditionally employed in international safeguards. This paper examines the modifications and innovations that might be required to the current international safeguards regime in meeting these proposed new roles. Although the examples given are in the context of the US materials and facilities, many of the conclusions are valid for other NWS. None of the statements in this paper represent official US position on policy for international safeguards in weapons states. Instead, the purpose is to identify policy and technical issues and to offer, where possible, options for their resolution. This paper limits consideration to the potential role of the IAEA in verifying these proposed initiatives for declared facilities, recognizing that there may also be a role for bilateral, multilateral, or regional verification regimes. Indeed, in some cases verification of weapons materials may be more appropriate for a bilateral arrangement. Because traditional IAEA safeguards may not be admissible for weapons materials, the concept of ''transparency'' is suggested as a less intrusive alternative providing some confidence that materials are as declared

76 FR 57060 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2011-09-15

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... regulatory authorities and industry associations to promote the international harmonization of regulatory...

77 FR 20406 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2012-04-04

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... been developed for veterinary use by the International Cooperation on Harmonisation of Technical... industry associations to promote the international harmonization of regulatory requirements. FDA has...

78 FR 14308 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2013-03-05

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... been developed for veterinary use by the International Cooperation on Harmonisation of Technical... regulatory authorities and industry associations to promote the international harmonization of regulatory...

Technical aspects of high converter reactors

International Nuclear Information System (INIS)

1992-02-01

The meeting provided an opportunity to review and discuss national R and D programs, various technical aspects of and worldwide progress in the implementation of high conversion reactors. The meeting was attended by 66 participants from 18 countries and 2 international organizations. 33 papers were presented. A separate abstract was prepared for each of these papers. Refs, figs, tabs, slides and diagram

Validation procedures of software applied in nuclear instruments. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-09-01

The IAEA has supported the availability of well functioning nuclear instruments in Member States over more than three decades. Some older or aged instruments are still being used and are still in good working condition. However, those instruments may not meet modern software requirements for the end-user in all cases. Therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. New advanced software is not only applied in case of new instrumentation, but often also for new and improved applications of modernized and/or refurbished instruments in many Member States for which in few cases the IAEA also provided support. Modern software applied in nuclear instrumentation plays a key role for their safe operation and execution of commands in a user friendly manner. Correct data handling and transfer has to be ensured. Additional features such as data visualization, interfacing to PC for control and data storage are often included. To finalize the task, where new instrumentation which is not commercially available is used, or aged instruments are modernized/refurbished, the applied software has to be verified and validated. A Technical Meeting on 'Validation Procedures of Software Applied in Nuclear Instruments' was organized in Vienna, 20-23 November 2006, to discuss the verification and validation process of software applied to operation and use of nuclear instruments. The presentations at the technical meeting included valuable information, which has been compiled and summarized in this publication, which should be useful for technical staff in Member States when modernizing/refurbishing nuclear instruments. 22 experts in the field of modernization/refurbishment of nuclear instruments as well as users of applied software presented their latest results. Discussion sessions followed the presentations. This publication is the outcome of deliberations during the meeting

75 FR 18505 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2010-04-12

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... promote the international harmonization of regulatory requirements. FDA has participated in efforts to...

76 FR 57057 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2011-09-15

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... undertaken by regulatory authorities and industry associations to promote the international harmonization of...

76 FR 57058 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2011-09-15

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... has been developed for veterinary use by the International Cooperation on Harmonisation of Technical... been undertaken by regulatory authorities and industry associations to promote the international...

75 FR 18508 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2010-04-12

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... use by the International Cooperation on Harmonisation of Technical Requirements for Registration of... promote the international harmonization of regulatory requirements. FDA has participated in efforts to...

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

The Importance of International Technical Nuclear Forensics to Deter Illicit Trafficking

International Nuclear Information System (INIS)

Smith, D K

2007-01-01

, nuclear safeguards, and emerging civilian nuclear power initiatives including the Global Nuclear Energy Partnership are crucial components of a successful nuclear detection and security architecture. Once illicit shipments of nuclear material are discovered at a border, the immediate next question will be the nature and the source of the material, as well as the identity of the individual(s) involved in the transfer as well as their motivations. The Nuclear Smuggling International Technical Working Group (ITWG) is a forum for the first responder, law enforcement, policy, and diplomatic community to partner with nuclear forensics experts worldwide to identify requirements and develop technical solutions in common. The ITWG was charted in 1996 and since that time approximately 30 member states and organizations have participated in 11 annual international meetings. The ITWG also works closely with the IAEA to provide countries with support for forensic analyses. Priorities include the development of common protocols for the collection of nuclear forensic evidence and laboratory investigations, organization of forensic round-robin analytical exercises and technical forensic assistance to requesting nations. To promote the science of nuclear forensics within the ITWG the Nuclear Forensics Laboratory Group was organized in 2004. A Model Action Plan for nuclear forensics was developed by the ITWG and published as an IAEA Nuclear security Series document to guide member states in their own forensics investigations. Through outreach, formalized partnerships, common approaches and security architectures, and international working groups, nuclear forensics provides an important contribution to promoting nuclear security and accountability

78 FR 14306 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2013-03-05

...]; (Formerly Docket No. 00D-1631)] International Cooperation on Harmonisation of Technical Requirements for... for veterinary use by the International Cooperation on Harmonisation of Technical Requirements for... regulatory authorities and industry associations to promote the international harmonization of regulatory...

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

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

Ninth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Raeder, J.; Gordon, C.

2001-01-01

The ninth ITER Technical Meeting on safety and environment, the last in the course of the ITER Engineering Design Activities (EDA), was held at the ITER Garching Joint Work site, 8 to 10 May 2001. At this Meeting, safety experts from the House Teams worked together with the members of the Safety, Environment and Health Groups (SEHG) of the ITER Joint Central Team (JCT) in the following areas: finalization of the Generic Site Safety report (GSSR) which is considered to be the most important objective of the present work; summary of the safety related R and D work done by the Home Teams for ITER during EDA; review of verification and validation work done on computer codes being applied for Safety and Environment (S and E) analyses; outline of work considered necessary for improving the S and E database, quantifying uncertainties of the code results and preparing the adaptation of ITER to a specific site

Technical memory 2007

International Nuclear Information System (INIS)

2009-01-01

The technical memory 2007 of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, compiles the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialities by personnel of the mentioned institution during 2007. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management [es

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

International Nuclear Information System (INIS)

Vitikainen, E.; Silfverberg, P.

1985-01-01

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

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

Tenth meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation, Vienna, 3-5 March 1986

International Nuclear Information System (INIS)

1986-07-01

The meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of NPP control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The papers and discussions mostly dealt with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economic aspects of the introduction of modern, highly automated control systems and on the improvement of plant availability and safety. A separate abstract was prepared for each of the 20 presentations of the meeting

Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

International Nuclear Information System (INIS)

Fabian, H.

2004-01-01

The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de

International Working Group on Fast Reactors Second Annual Meeting. Summary Report

International Nuclear Information System (INIS)

1969-01-01

The Agenda of the Meeting was as follows: Opening of the meeting. 2. Appraisal of the IWGFB's activity for the period from the first annual meeting of the Group. 3. Comments on national programmes on fast breeder reactors. 4. Presentation of general findings and conclusions of national and regional meetings on fast reactor problems held in represented countries and international organisations last year. 5. Comments on the programmes of international meetings on fast reactors to be held in 1969. 6. Consideration of a schedule for meetings on fast reactors in 1970. 7. Suggestions for the topics and location of specialists' meetings in 1969-1970. 8. Suggestions for reviews and studies in the field of fast reactors. 9. The time and place of the third annual meeting of the IWGFR. 10. Closing of the meeting

Internet and Audiology: A Review of the First International Meeting.

Science.gov (United States)

Andersson, Gerhard; Lunner, Thomas; Laplante-Lévesque, Ariane; Preminger, Jill E

2015-09-01

The purpose of this research forum article is to describe the impetus for holding the First International Meeting on Internet and Audiology (October 2014) and to introduce the special research forum that arose from the meeting. The rationale for the First International Meeting on Internet and Audiology is described. This is followed by a short description of the research sections and articles appearing in the special issue. Six articles consider the process of health care delivery over the Internet; this includes health care specific to hearing, tinnitus, and balance. Four articles discuss the development of effective Internet-based treatment programs. Six articles describe and evaluate Internet-based interventions specific to adult hearing aid users. The fledgling field of Internet and audiology is remarkably broad. The Second International Meeting on Internet and Audiology ocurred in September 2015.

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.

Meeting of the ITER CTA Project Board

International Nuclear Information System (INIS)

2001-01-01

Full text: A preparatory meeting of the Co-ordinated Technical Activities (CTA) Project Board took place in Vienna on 16 July 2001. The Board Members of Canada, EU, Japan, RF and of the CTA International Team participated in the Meeting, which was chaired by Acad. E. Velikhov. The major item on the Meeting Agenda was the discussion of the scope of the CTA. In this discussion the following comments were expressed: One of the prime objectives during the CTA is to develop technical specifications for procurement of critical items (magnets, vacuum vessel, and buildings). It was noted that the discussions with potential suppliers should confirm manufacturing processes in details in order to explore possible schedule reduction strategies. Safety analysis and licensing preparation should proceed on all proposed sites up to the preferred site designation, to ensure the overall implementation schedule is minimized and to resolve major technical issues needed for licensing. Several R and D issues remain to be further developed during the CTA. Special attention should be given by the Participants to two areas: Diagnostics; Heating and Current Drive Systems. Arrangements for continuation of the ITER Physics Expert Groups activities should be provided. To this end a new framework, called International Tokamak Physics Activity, is being planned. The Board encouraged the Participants' Representatives in the Co-ordinating committee of this activity to support the preparation for urgent Topical Group Meetings. The Board agreed that the Design Authority will be invested in the International Team and that proposals for site specific design changes should be agreed upon by the International Team Leader before being studied in detail. The Meeting agreed on some arrangements which will remain from the EDA, namely the ITER EDA Council Office in Moscow as Office of the PB Chair, and the ITER Office located at the IAEA in Vienna as agreed by the IAEA. The Board recommended that effective

English as a lingua franca used at international meetings

Directory of Open Access Journals (Sweden)

Barančicová Jana

2015-09-01

Full Text Available The paper deals with the use of English as a lingua franca. It concentrates on the environment of international meetings where English is used as a lingua franca. The aim of the research conducted through a survey of members of a NATO working group is to find out how native and non-native speakers feel about English used as a lingua franca during international meetings and how these two groups of speakers see each other in multinational interaction from the point of view of linguistics. The sections dealing with non-native speakers concentrate on the level of knowledge of English and on how native speakers cope with the English used during the meetings. The sections dealing with the views of English native speakers should establish the approach they take towards mistakes made by non-native speakers, whether native speakers should adjust the way they speak at international meetings and how they generally view the fact that their mother tongue is used all around the world.

Internet and Audiology: A Review of the Second International Meeting.

Science.gov (United States)

Laplante-Lévesque, Ariane; Lunner, Thomas; Andersson, Gerhard; Preminger, Jill E

2016-10-01

This article describes the Second International Meeting on Internet and Audiology, which took place at the Eriksholm Research Centre, Oticon A/S, Denmark September 24 to 25, 2015, and introduces the research forum arising from the meeting. The potential gains of the Internet within audiology are framed within the central role of quality connections among people, ideas, and objects. First, the meeting is summarized. Second, the 11 articles arising from the meeting and collected in this research forum are grouped into 2 themes: design and evaluation. Last, the benefits of interoperability and standardization are discussed. We look forward to the day when the Internet is an integral part of audiology, and we invite readers to attend future editions of the International Meeting on Internet and Audiology.

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

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

International Working Group on Fast Reactors Sixth Annual Meeting. Summary Report

International Nuclear Information System (INIS)

1973-01-01

The Agenda of the Meeting was as follows: 1. Review of IWGFR Activities - 1a. Approval of the minutes of the Fifth IWGFR Meeting. 1b. Report by Scientific Secretary regarding the activities of the Group. 2. Comments on National Programmes on Fast Breeder Reactors. 3. International Coordination of the Schedule for Major Fast Reactor Meetings and other major international meetings having a predominant fast reactor interest. 4. Consideration of Conferences on Fast Reactors. 4a. IAEA Symposium on Fuel and Fuel Elements for Fast Reactors, Brussels, Belgium 2-6 July 1973. 4b. International Symposium on Physics of Fast Reactors, Tokyo, Japan, 16 to 23 October 1973. 4c. International Conference on Fast Reactor Power Stations, London, UK, 11 to 14 March 1974 . 4d. Suggestions of the IWGFR members on other conferences. 5. Consideration of a Schedule for Specialists' Meetings in 1973-74. 6. Other Business - 6a. First-aid in Sodium Burns. 6b. Principles of Good Practice for Safe Operation of Sodium Circuits. 6c. Bibliography on Fast Reactors. 7. The Date and Place of the Seventh Annual Meeting of the IWGFR

Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objective of the Technical Meeting is to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials

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

IAEA advisory group meeting on 'Technical Aspects of Atomic and Molecular Data Processing and Exchange' (14th meeting of the A + M data centres and ALADDIN network). Summary report

International Nuclear Information System (INIS)

Stephens, A.

1998-01-01

The proceedings of the IAEA Advisory Group Meeting on ''Technical Aspects of Atomic and Molecular Data Processing and Exchange (14th Meeting of A + M Data Centres and ALADDIN Network)'', held on July 21-22, 1997 in Vienna, Austria are briefly described. The meeting conclusions and recommendations on the priorities in A + M data compilation and evaluation, and on the technical aspects of data processing and exchange are also presented. The document includes 15 reports from various Data Centres

International Meeting on Simulation in Healthcare 2007

National Research Council Canada - National Science Library

Gordon, James; Anderson, Beverlee

2007-01-01

1200 individuals attended the 2007 International Meeting on Simulation in Healthcare and had access to panels, keynotes and workshop sessions to further their knowledge of use of simulation in health...

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

Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

International Nuclear Information System (INIS)

2013-04-01

The growing operational requirements for nuclear fuel, such as longer fuel cycles, higher burnups and wider use of transient regimes, require more robust fuel designs and more radiation resistant materials. Development of such advanced fuels is only possible with testing and analysis of their performance and application of adequate post-irradiation examination (PIE) methods and techniques. In addition, operational feedback data from poolside and PIE facilities are absolutely necessary for verification of fuel modelling codes and analysis of fuel failure mechanisms. For these reasons, the International Atomic Energy Agency (IAEA) has supported the international exchange of knowledge and sharing of best practices in the application of modern destructive and non-destructive methods of investigation of highly radioactive materials through a series of technical meetings (TMs), the last of which was held in 2006 in Buenos Aires. Since 1963, similar meetings, initially at the European level, have been organized by the Hot Laboratories and Remote Handling Working Group (HOTLAB), a partner in the development of the IAEA's Post Irradiation Examination Facilities Database (PIEDB), part of the IAEA's Integrated Nuclear Fuel Cycle Information System. With this successful partnership in mind, in 2010 the IAEA Technical Working Group on Fuel Performance and Technology recommended that a joint IAEA-HOTLAB TM be held on 'Hot Cell Post-Irradiation Examination and Pool-Side Inspection of Nuclear Fuel', covering questions relevant to the IAEA sub-programmes on 'Nuclear Power Reactor Fuel Engineering' and 'Management of Spent Fuel from Nuclear Power Reactors'. The TM was held on 23-27 May 2011, in Smolenice, Slovakia, with the participation of a large number of interested organizations and comprehensive coverage of major PIE and poolside inspection issues relating to both operation and storage of fuel for nuclear power reactors. The proceedings, summaries and conclusions of that joint

'Nuclex 75'. Preview of the technical fair

International Nuclear Information System (INIS)

Anon.

1975-01-01

The 'Nuclex 75' - fourth international technical fair and specialist meetings for the nuclear industry - takes place from the 7th to the 11th October 1975 in the halls of the Schweizer Mustermesse in Basel. The meeting, which has taken place at three-yearly intervals since 1966, is divided into a technical fair and a congress. 422 exhibitors from 25 countries take part in the 'Nuclex 75'. Several industrial countries are again represented by communal exhibitions. The editorial office of 'Atom and Electricity' gives a few hints on the technical fair to follow which are based on the papers of the exhibitor sent in up to the editor's closing date. A detailed report on the technical fair as well as on important topics of the congress will appear in volume 11/12 1975. (orig./LH) [de

IAEA technical meeting on nuclear data library for advanced systems - Fusion devices

International Nuclear Information System (INIS)

Forrest, R.; Mengoni, A.

2008-04-01

A Technical Meeting on 'Nuclear Data Library for Advanced Systems - Fusion Devices' was held at the IAEA Headquarters in Vienna from 31 October to 2 November 2007. The main objective of the initiative has been to define a proposal and detailed plan of activities for a Co-ordinated Research Project on this subject. Details of the discussions which took place at the meeting, including a review of the current activities in the field, a list of recommendations and a proposed timeline schedule for the CRP are summarized in this report. (author)

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

International Nuclear Information System (INIS)

2015-01-01

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

Proceedings of international conference dedicated to the seventieth anniversary of Physical-technical institute, SPA 'Physics-Sun' 'Fundamental and applied problems of physics'

International Nuclear Information System (INIS)

Lutpullaev, S.L.; Atabaev, I.G.; Abdurakhmanov, A.A.

2013-11-01

The International conference dedicated to the seventieth anniversary of Physical-technical institute, SPA 'Physics-Sun' 'Fundamental and applied problems of physics' was held on 14-15 November, 2013 in Tashkent, Uzbekistan. Specialists discussed various aspects of modern problems of relativistic nuclear physics and physics of atomic nuclei, solid state physics, various applications of new materials. More than 225 talks were presented in the meeting. (k.m.)

Abstracts and papers of the 1996 International RERTR Meeting

International Nuclear Information System (INIS)

1996-10-01

The 1996 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was sponsored by the Korea Atomic Energy Research Institute and the International Atomic Energy Agency and was held in Seoul, Korea, on 6-10 October 1996. The abstracts and available papers that were presented at this meeting are provided. The most important subject dealt with was progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program. The major events, findings, and activities of 1996 are reviewed with the results which the RERTR Program has achieved by the end of 1995 in collaboration of the ANL and its many international partners

Abstracts and papers of the 1996 International RERTR Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

The 1996 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was sponsored by the Korea Atomic Energy Research Institute and the International Atomic Energy Agency and was held in Seoul, Korea, on 6-10 October 1996. The abstracts and available papers that were presented at this meeting are provided. The most important subject dealt with was progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program. The major events, findings, and activities of 1996 are reviewed with the results which the RERTR Program has achieved by the end of 1995 in collaboration of the ANL and its many international partners.

Commercial products and services of research reactors. Proceedings of a technical meeting held in Vienna 28 June - 2 July 2010

International Nuclear Information System (INIS)

2013-07-01

the utilization of research reactors and their sustainability through financially viable services and international cooperation. In this report, reference is also made to a similar IAEA technical meeting on 'Commercial Applications of Nuclear Analytical Techniques', held in Vienna, Austria, from 23 to 26 November 2004, and a few recently updated papers from that meeting have been included here. This publication summarizes the individual reports presented during the above meetings, and details the overall findings and conclusions jointly identified and agreed upon by the meeting participants. The individual papers are available on the CD-ROM attached to this publication

78 FR 33416 - Notification of a Public Meeting of the Science Advisory Board Environmental Justice Technical...

Science.gov (United States)

2013-06-04

... ENVIRONMENTAL PROTECTION AGENCY [FRL--9819-3] Notification of a Public Meeting of the Science... Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces a public meeting of the SAB Environmental Justice Technical Guidance Review Panel to provide advice through...

ICFA: Protvino meeting looks at trends in international collaboration

Energy Technology Data Exchange (ETDEWEB)

Anon.

1991-01-15

International collaboration is the lifeblood of Big Science, and in high energy physics the triennial 'Future Perspectives' meeting organized by the International Committee for Future Accelerators (ICFA) provides a valuable opportunity to reappraise trends in this collaboration. The latest meeting was held in October at Protvino, near Moscow, where the Institute for High Energy Physics is the scene of construction work for the 21-kilometre UNK proton rings and the projected home of a big new linear collider for electrons and positrons.

76 FR 16785 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

Science.gov (United States)

2011-03-25

... designed as an interactive forum where PSOs and software developers can provide input on these technical... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability.... Throughout the meeting there will be interactive discussion to allow meeting participants not only to provide...

76 FR 57054 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2011-09-15

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... (MRK),'' (VICH GL46). This guidance has been developed for veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal Products (VICH...

Electrical and Electronics Technical Team Roadmap

Energy Technology Data Exchange (ETDEWEB)

None

2013-06-01

The Electrical and Electronics Technical Team’s (EETT's) mission is to enable cost-effective, smaller, lighter, and efficient power electronics and electric motors for electric traction drive systems (ETDSs) while maintaining performance of internal combustion engine (ICE)-based vehicles. The EETT also identifies technology gaps, establishes R&D targets, develops a roadmap to achieve technical targets and goals, and evaluates the R&D progress toward meeting the established R&D targets and goals.

2011 Residential Energy Efficiency Technical Update Meeting Summary Report: Denver, Colorado - August 9-11, 2011

Energy Technology Data Exchange (ETDEWEB)

2011-11-01

This report provides an overview of the U.S. Department of Energy Building America program's Summer 2011 Residential Energy Efficiency Technical Update Meeting. This meeting was held on August 9-11, 2011, in Denver, Colorado, and brought together more than 290 professionals representing organizations with a vested interest in energy efficiency improvements in residential buildings.

The international linear collider. Technical design report. Vol. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi (eds.)

2013-07-01

A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

The international linear collider. Technical design report. Vol. 1. Executive summary

International Nuclear Information System (INIS)

Behnke, Ties; Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; McEwan Paterson, James; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi

2013-01-01

A review is given about the planned International Linear Collider. Especially described are the technical design, the accelerator layout and design, the R and D during the technical design phase, and the detectors. (HSI)

ICFA: Protvino meeting looks at trends in international collaboration

International Nuclear Information System (INIS)

Anon.

1991-01-01

International collaboration is the lifeblood of Big Science, and in high energy physics the triennial 'Future Perspectives' meeting organized by the International Committee for Future Accelerators (ICFA) provides a valuable opportunity to reappraise trends in this collaboration. The latest meeting was held in October at Protvino, near Moscow, where the Institute for High Energy Physics is the scene of construction work for the 21-kilometre UNK proton rings and the projected home of a big new linear collider for electrons and positrons

Technical Report 2000

International Nuclear Information System (INIS)

2001-01-01

The technical memory 2000 of the Nuclear Regulatory Authority (NRA) of the Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, safeguards and physical protection, and presented in congress or meetings of these specialities by personnel of the mentioned institution during 2000. In this edition the documents are presented on: Nuclear safety; Radiobiology; Occupational doses; Radiochemical; Environmental studies; Emergency plans; Radiation accidents; and International safeguards. Some of them are realized by agreements between the Nuclear Regulatory Authority of Argentina, universities and other national and international organizations

Space Solar Power Technical Interchange Meeting 2: SSP TIM 2

Science.gov (United States)

Sanders, Jim; Hawk, Clark W.

1998-01-01

The 2nd Space Solar Power Technical Interchange Meeting (SSP TIM 2) was conducted September 21st through 24th with the first part consisting of a Plenary session. The summary results of this Plenary session are contained in part one of this report. The attendees were then organized into Working Breakout Sessions and Integrated Product Team (IPT) Sessions for the purpose of conducting in-depth discussions in specific topic areas and developing a consensus as to appropriate study plans and actions to be taken. The Second part covers the Plenary Summary Session, which contains the summary results of the Working Breakout Sessions and IPT Sessions. The appendix contains the list of attendees. The ob'jective was to provide an update for the study teams and develop plans for subsequent study activities. This SSP TIM 2 was initiated and the results reported electronically over the Internet. The International Space Station (ISS) could provide the following opportunities for conducting research and technology (R&T) which are applicable to SSP: (1) Automation and Robotics, (2) Advanced Power Generation, (3) Advanced Power Management & Distribution (PMAD), (4) Communications Systems and Networks, (5) Energy Storage, (6) In Space Propulsion (ISP), (7) Structural Dynamics and Control, and Assembly and (8) Wireless Power Transmission.

Contact expert group for international radwaste projects. Fourth meeting

International Nuclear Information System (INIS)

1997-06-01

The Contact Expert Group for International Radwaste Projects is the result of an IAEA seminar on ''International Co-operation on Nuclear Waste Management in the Russian Federation'', 15-17 May 1995, that was requested and sponsored by the Nordic countries. In two working groups at the Seminar, participants from the Russian Federation and 17 countries and international organizations co-operating with the Russian Federation in waste management projects recognized the need for setting up a contact group of experts to assist in co-ordinating their efforts. Such co-ordination would help avoid redundancy and duplication of effort, assure that priority needs were made known to the international community, and provide points of contact to facilitate co-operation. This report is a compilation of the 4. CEG meeting materials, both prepared by the CEG Secretariat and presented by meeting's participants. The materials discussed by the CEG and subsequently modified are presented in the finally approved version. As in the case of previous similar reports, the documentation presented was just compiled without any editing and thus should be considered only as ''working proceedings'' of the meeting

75 FR 32798 - Preparation for International Cooperation on Cosmetic Regulations; Public Meeting

Science.gov (United States)

2010-06-09

... cosmetics' industry trade associations. Currently, the ICCR members are Health Canada; the European... for International Cooperation on Cosmetic Regulations; Public Meeting AGENCY: Food and Drug... public meeting entitled ``International Cooperation on Cosmetic Regulations (ICCR)--Preparation for ICCR...

78 FR 20662 - Preparation for International Cooperation on Cosmetics Regulation; Public Meeting

Science.gov (United States)

2013-04-05

... authority members will enter into constructive dialogue with their relevant cosmetics industry trade...] Preparation for International Cooperation on Cosmetics Regulation; Public Meeting AGENCY: Food and Drug... public meeting entitled, ``International Cooperation on Cosmetics Regulation (ICCR)--Preparation for ICCR...

76 FR 18767 - Preparation for International Cooperation on Cosmetics Regulations; Public Meeting

Science.gov (United States)

2011-04-05

... cosmetics' industry trade associations. Currently, the ICCR members are Health Canada; the European...] Preparation for International Cooperation on Cosmetics Regulations; Public Meeting AGENCY: Food and Drug... announcing a public meeting entitled ``International Cooperation on Cosmetics Regulations (ICCR)--Preparation...

Recent developments in uranium resources and production with emphasis on in situ leach mining. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2004-06-01

An important role of the International Atomic Energy Agency is establishing contacts between Member States in order to foster the exchange of scientific and technical information on uranium production technologies. In situ leach (ISL) mining is defined as, the extraction of uranium from the host sandstone by chemical solutions and the recovery of uranium at the surface. ISL extraction is conducted by injecting a suitable leach solution into the ore zone below the water table; oxidizing, complexing, and mobilizing the uranium; recovering the pregnant solutions through production wells; and, finally, pumping the uranium bearing solution to the surface for further processing. As compared with conventional mining, in situ leach is recognized as having economic and environmental advantages when properly employed by knowledgeable specialists to extract uranium from suitable sandstone type deposits. Despite its limited applicability to specific types of uranium deposits, in recent years ISL uranium mining has been producing 15 to 21 per cent of world output. In 2002, ISL production was achieved in Australia, China, Kazakhstan, the United States of America and Uzbekistan. Its importance is expected to increase with new projects in Australia, China, Kazakhstan and the Russian Federation. The Technical Meeting on Recent Development in Uranium Resources and Production with Special Emphasis on In Situ Leach Mining, was held in Beijing from 18 to 20 September 2002, followed by the visit of the Yili ISL mine, Xinjiang Autonomous Region, China, from 21 to 23 September 2002. The meeting, held in cooperation with the Bureau of Geology, China National Nuclear Cooperation, was successful in bringing together 59 specialists representing 18 member states and one international organization (OECD/Nuclear Energy Agency). The papers describe a wide variety of activities related to the theme of the meeting. Subjects such as geology, resources evaluation, licensing, and mine restoration were

NASA Docking System (NDS) Technical Integration Meeting

Science.gov (United States)

Lewis, James L.

2010-01-01

This slide presentation reviews the NASA Docking System (NDS) as NASA's implementation of the International Docking System Standard (IDSS). The goals of the NDS, is to build on proven technologies previously demonstrated in flight and to advance the state of the art of docking systems by incorporating Low Impact Docking System (LIDS) technology into the NDS. A Hardware Demonstration was included in the meeting, and there was discussion about software, NDS major system interfaces, integration information, schedule, and future upgrades.

76 FR 58332 - Announcement of Meeting of the International Telecommunication Advisory Committee

Science.gov (United States)

2011-09-20

..., NW., Washington, DC 20520, to seek further advice from the telecommunications industry on (a) whether... DEPARTMENT OF STATE [Public Notice: 6869] Announcement of Meeting of the International Telecommunication Advisory Committee Summary: This notice announces a meeting of the International Telecommunication...

19th Meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary Report of an IAEA Technical Meeting

International Nuclear Information System (INIS)

Braams, Bastiaan J.

2014-07-01

The International Fusion Research Council (IFRC) Subcommittee on Atomic and Molecular Data met at IAEA Headquarters in Vienna on 28-29 April 2014 to review the work of the Atomic and Molecular Data Unit (AMDU) within the Nuclear Data Section. The subcommittee heard presentations on the Unit’s activities in the years 2012 and 2013 and discussed priorities for database development and evaluation, coordinated research projects and other meetings, and presentation on the web and elsewhere of the work of the Unit. The IFRC Subcommittee offers the following specific recommendations. • For Coordinated Research Projects in the area of plasma-material interaction highest priority goes to a CRP on erosion and tritium retention for steel surfaces, with emphasis on the kinds of low- or reduced-activation steels that may be used in a reactor. • In the area of atomic and molecular data it is recommended to initiate a new CRP on data for charge exchange processes related to neutral beams. The main topic of interest will be beam interaction with core plasma, but processes relevant to generation of the beam may also be included. • Data for plasma interaction with liquid metals gallium and tin, certain salts and possibly also aluminium, are needed in order to assess uses of these materials in a reactor environment. For a CRP this topic has lower priority than one on steel surfaces, but it is recommended as a good topic for a Technical Meeting. • The Unit should organize again, in 2014 or early 2015, a large “decennial” meeting on atomic, molecular and plasma-material interaction data for fusion science and technology to bring together fusion scientists users of A+M+PMI data and atomic, molecular and materials scientists data producers. • The Unit has the mission to provide internationally recommended and evaluated data for atomic, molecular and plasma-material interaction process and related materials structure properties for fusion science and technology; this is

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

An Online Approach to Teaching International Outsourcing in Technical Communication Classes

Science.gov (United States)

St. Amant, Kirk

2005-01-01

The growth of international online access has given rise to a new production method--international outsourcing--that has important implications for technical communication practices. Successful interactions within international outsourcing require individuals to understand how cultural factors could affect online interactions. Today's technical…

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

Proceedings of the Twentieth International Microgravity Measurements Group Meeting

Science.gov (United States)

DeLombard, Richard (Compiler)

2001-01-01

The International Microgravity Measurements Group annual meetings provide a forum for an exchange of information and ideas about various aspects of microgravity acceleration research in international microgravity research programs. These meetings are sponsored by the PI Microgravity Services (PIMS) project at the NASA Glenn Research Center. The twentieth MGMG meeting was held 7-9 August 2001 at the Hilton Garden Inn Hotel in Cleveland, Ohio. The 35 attendees represented NASA, other space agencies, universities, and commercial companies; eight of the attendees were international representatives from Canada, Germany, Italy, Japan, and Russia. Seventeen presentations were made on a variety of microgravity environment topics including the International Space Station (ISS), acceleration measurement and analysis results, science effects from microgravity accelerations, vibration isolation, free flyer satellites, ground testing, and microgravity outreach. Two working sessions were included in which a demonstration of ISS acceleration data processing and analyses were performed with audience participation. Contained within the minutes is the conference agenda which indicates each speaker, the title of their presentation, and the actual time of their presentation. The minutes also include the charts for each presentation which indicate the author's name(s) and affiliation. In some cases, a separate written report was submitted and has been included here.

Meeting of the ITPA Topical Group on Diagnostics

International Nuclear Information System (INIS)

Costley, A.E.; Donne, A.J.H.

2002-01-01

The first meeting of the International Tokamak Physics Activities (ITPA) Topical Group (TG) on diagnostics was held at the Ioffe Physical-Technical institute, St. Petersburg, Russian Federation, on 14-16 November 2001. In total 38 participants attended the meeting and all four ITPA partners (EU, JA, RF and US) were represented. This summary covers mainly the discussions at the TG meeting. The meeting immediately followed a progress meeting, held in the same location on 12-13 November 2001, on the efforts carried out in the Russian Federation on diagnostics for ITER and burning plasma experiments

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...

Structural behaviour of fuel assemblies for water cooled reactors. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-07-01

At the invitation of the Government of France and in response to a proposal of the IAEA Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT), the IAEA convened a Technical Meeting on Fuel Assembly Structural Behaviour in Cadarache, France, from 22 to 26 November 2004. The meeting was hosted by the CEA Cadarache Centre, AREVA Framatome-ANP and Electricite de France. The meeting aimed to provide in depth technical exchanges on PWR and WWER operational experience in the field of fuel assembly mechanical behaviour and the potential impact of future high burnup fuel management on fuel reliability. It addressed in-service experience and remedial solutions, loop testing experience, qualification and damage assessment methods (analytic or experimental ones), mechanical behaviour of the fuel assembly including dynamic and fluid structure interaction aspects, modelling and numerical analysis methods, and impact of the in-service evolution of the structural materials. Sixty-seven participants from 17 countries presented 30 papers in the course of four sessions. The topics covered included the impact of hydraulic loadings on fuel assembly (FA)performance, FA bow and control rod (CR) drop kinetics, vibrations and rod-to-grid wear and fretting, and, finally, evaluation and modelling of accident conditions, mainly from seismic causes. FA bow, CR drop kinetics and hydraulics are of great importance under conditions of higher fuel duties including burnup increase, thermal uprates and longer fuel cycles. Vibrations and rod-to-grid wear and fretting have been identified as a key cause of fuel failure at PWRs during the past several years. The meeting demonstrated that full-scale hydraulic tests and modelling provide sufficient information to develop remedies to increase FA skeleton resistance to hydraulic loads, including seismic ones, vibrations and wear. These proceedings are presented as a book with an attached CD-ROM. The first part of the CD

Characterization and testing of materials for nuclear reactors. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-03-01

Nuclear techniques in general and neutrons based methods in particular have played and will continue to play an important role in research in materials science and technology. Today the world is looking at nuclear fission and nuclear fusion as the main sources of energy supply for the future. Research reactors have played a key role in the development of nuclear technology. A materials development programme will thus play a major role in the design and development of new nuclear power plants, for the extension of the life of operating reactors as well as for fusion reactors. Against this background, the IAEA had organized a Technical Meeting on Development, Characterization and Testing of Materials - With Special Reference to the Energy Sector under the activity on specific applications of research reactors. The meeting was held in Vienna, May 29- June 2, 2006. There was also participation by experts in techniques, complementary to neutrons. The participants for the technical meeting were experts in the utilization of nuclear techniques namely the high flux and medium flux research reactors, fusion research and positron annihilation. They presented the design, development and utilization of the facilities at their respective centres for materials characterization with main focus on materials for nuclear energy, both fission and fusion. In core irradiation of materials, development of instrument for residual stress measurement in large and / or irradiated specimen, neutron radiography for inspection of irradiated fuel, work on oxide dispersion strengthened (ODS) steels and SiC composites, relevant to future power systems were cited as application of nuclear techniques in fission reactors. The use of neutron scattering for helium bubbles in steel, application of positron annihilation to study helium bubbles in Cu, Ti-stabilized stainless steel and voidswelling studies etc. show that these techniques have an important role in the development of materials for energy

Technical Memory 2010. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2010-01-01

The technical memory 2010 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2010. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

Technical Memory 2011. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2011-01-01

The technical memory 2011 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2011. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

Report of the 6th International Exchange Mission on visit to the U.S. Centering on participation in the ASHRAE Winter Meeting; Dai 6 kai kokusai koryu shisatsudan hobei hokoku (ASHRAE Winter Meeting sanka wo chushin to shite)

Energy Technology Data Exchange (ETDEWEB)

Tanaka, T. [Ochanomizu Univ., Tokyo (Japan)

1997-08-05

This paper describes a summary of the ASHRAE Winter Meeting and other tours in which 18 members of the Society of Heating, Air-Conditioning and Sanitary Engineers of Japan have participated. The Winter Meeting adopted five patterns of publication: a technical session, symposia, seminars, forums and a poster session. The number of reports given in respective patterns were 20, 57, 131, 34 and 20. In the technical session, Professor Murakami from Japan presented a report titled `flow and temperature field around a human body in a room - a thermal mannequin using CFD`. At the same time, the International Airconditioning, Heating, Refrigerating Exposition was held. Interesting exhibitions included a data communication protocol, BACnet, for a network of automation and control of buildings, software for technical drawings presented by Visio Corporation, the Metasys FMS of Jonson Controls Corporation, and a single-stage screw freezing machine using a coolant having zero ozonosphere destruction coefficient exhibited by Mcquay Corporation. The visiting members attended an environmental preservation seminar by Walt Disney World Corporation. 8 figs., 1 tab.

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

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

Technical meeting (TM) to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Technical Working Group on Fast Reactors (TWG-FR) (37th annual meeting). Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The objectives of the 37th Annual Meeting of the Technical Working Group on Fast Reactors, were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 36th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2004 and 2005; 4) review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations. The participants made presentations on the status of the respective national programmes on FR and ADS development. A summary of the highlights for the period since the 36th TWG-FR Annual Meeting is included in this proceedings. Annex IV contains the Review of National Programs on Fast Reactors and Accelerator Driven Systems (ADS), and the TWG-FR Activity Report for the Period May 2003-April 2004.

Report on the consultants` meeting on technical aspects of the co-operation of nuclear reaction data centers

Energy Technology Data Exchange (ETDEWEB)

Lemmel, H D; Schwerer, O; Wienke, H [eds.

1995-10-01

The IAEA Nuclear Data Section convenes in annual intervals coordination meetings of the Network of the Nuclear Reaction Data Center. The present meeting dealt with technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Refs, figs and tabs.

Report on the consultants' meeting on technical aspects of the co-operation of nuclear reaction data centers

International Nuclear Information System (INIS)

Lemmel, H.D.; Schwerer, O.; Wienke, H.

1995-10-01

The IAEA Nuclear Data Section convenes in annual intervals coordination meetings of the Network of the Nuclear Reaction Data Center. The present meeting dealt with technical matters of the nuclear data compilation and exchange by means of the jointly operated computerized systems CINDA, EXFOR, ENDF and others. Refs, figs and tabs

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

IAEA technical meeting: 13th meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary report

International Nuclear Information System (INIS)

Clark, R.E.H.; Peacock, N.J.

2002-11-01

This report briefly describes the proceedings, conclusions and recommendations of the 13th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council held on 24-25 June, 2002 at the IAEA Headquarters in Vienna Austria. The report includes an Executive Summary of the Subcommittee from this Meeting. (author)

Fifteenth annual meeting of the International Working Group on Fast Reactors. Summary report

International Nuclear Information System (INIS)

1982-09-01

The Fifteenth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous Annual Group Meeting, in Obninsk, USSR, Vienna from 30 March to 2 April 1982. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors

Sixteenth annual meeting of the International Working Group on Fast Reactors. Summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-10-01

The Sixteenth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous Annual Meeting Group, in Vienna from 12-15 April 1983. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors.

Fifteenth annual meeting of the International Working Group on Fast Reactors. Summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

1982-09-01

The Fifteenth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous Annual Group Meeting, in Obninsk, USSR, Vienna from 30 March to 2 April 1982. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors.

Sixteenth annual meeting of the International Working Group on Fast Reactors. Summary report

International Nuclear Information System (INIS)

1983-10-01

The Sixteenth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous Annual Meeting Group, in Vienna from 12-15 April 1983. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors

76 FR 75599 - Advisory Committee on International Economic Policy; Notice of Meeting Cancellation

Science.gov (United States)

2011-12-02

... DEPARTMENT OF STATE [Public Notice: 7659] Advisory Committee on International Economic Policy; Notice of Meeting Cancellation The meeting of the Advisory Committee on International Economic Policy... Tiffany Enoch, Office of Economic Policy Analysis and Public Diplomacy, Bureau of Economic, and Business...

[Fortieth Annual] Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2008-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 39th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2007, 2008 and 2009; - Review the Agency’s ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations; - Discuss future joint activities in view of the Agency’s Programme and Budget Cycle 2008–2009 (and beyond)

International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings

International Nuclear Information System (INIS)

1988-01-01

The seismic verification of nuclear plants is a subject of increasing interest in all the industrial countries, with respect to both the safety aspects and the impact of the seismic event on the design and the costs of a nuclear reactor. This topic is especially of great interest for a country like Italy, whose territory is unfortunately characterized by non - negligible seismicity: we remember, not too many years ago, the catastrophic earthquakes of Frioul and Irpinia, that caused thousands of dead people. The meeting aimed at establishing the state-of-the-art on on-site testing of nuclear reactors structures and components, with particular attention to experiences and research programmes concerning: methodologies of on-site tests and interpretation of the experimental data; seismic monitoring systems, recorded data, their use and interpretation; calibration and validation of numerical analyses. Six technical sessions were held, during which 23 high papers were presented and discussed, and six panel discussions were held (the importance of discussion was emphasized in the meeting). The technical contributions consisted of: an introduction paper, summarizing the seismic studies performed in Italy for PEC reactor and explaining the reasons why on-site tests had been performed on this reactor; 6 invited lectures, one for each of the countries that are more deeply involved in seismic analysis, providing the state-of-the-art on the topics of interest for the meeting; 16 contributed papers dealing with more specific technical items, related to the various countries and international organizations

International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-07-01

The seismic verification of nuclear plants is a subject of increasing interest in all the industrial countries, with respect to both the safety aspects and the impact of the seismic event on the design and the costs of a nuclear reactor. This topic is especially of great interest for a country like Italy, whose territory is unfortunately characterized by non - negligible seismicity: we remember, not too many years ago, the catastrophic earthquakes of Frioul and Irpinia, that caused thousands of dead people. The meeting aimed at establishing the state-of-the-art on on-site testing of nuclear reactors structures and components, with particular attention to experiences and research programmes concerning: methodologies of on-site tests and interpretation of the experimental data; seismic monitoring systems, recorded data, their use and interpretation; calibration and validation of numerical analyses. Six technical sessions were held, during which 23 high papers were presented and discussed, and six panel discussions were held (the importance of discussion was emphasized in the meeting). The technical contributions consisted of: an introduction paper, summarizing the seismic studies performed in Italy for PEC reactor and explaining the reasons why on-site tests had been performed on this reactor; 6 invited lectures, one for each of the countries that are more deeply involved in seismic analysis, providing the state-of-the-art on the topics of interest for the meeting; 16 contributed papers dealing with more specific technical items, related to the various countries and international organizations.

Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

International Nuclear Information System (INIS)

2013-01-01

The discussion which followed the different presentations highlighted the following points: • All the Member States representatives participating in the technical meeting welcomed this IAEA initiative and expressed their potential interest in contributing to the catalogue; • Not all the countries with a fast reactor programme were represented at the meeting. In particular, it was noted that there was no participation from China, the Russian Federation and the USA. Even contribution from Sweden and Spain would be beneficial. It will be a task of the IAEA Secretariat to try involving also these countries in the preparation of the catalogue; • The catalogue will focus only on experimental facilities supporting development of liquid metal cooled fast reactors (Sodium, Lead and Lead-Bismuth). For the time being, facilities in support of GFR and MSR research will not be included; • As for countries involved in HLM technology research, only European countries were participating at the meeting, i.e. Belgium, France, Italy and Germany. In order to avoid duplication of the work performed within the European project ADRIANA, representatives from these countries underlined that a condition for their contribution to the IAEA catalogue is the involvement of non-European countries with HLM research programmes; • The advice from the Member States is fundamental to clearly define scope, objectives and content of the catalogue. The plan for its drafting has also to be further discussed with Member States representatives; • The catalogue is also intended to identify gaps and future needs that require further R&D initiatives; • The catalogue will be a useful tool to set up international collaboration

Molecular markers predicting radiotherapy response: Report and recommendations from an International Atomic Energy Agency technical meeting

International Nuclear Information System (INIS)

West, Catharine M.L.; McKay, Michael J.; Hoelscher, Tobias; Baumann, Michael; Stratford, Ian J.; Bristow, Robert G.; Iwakawa, Mayumi; Imai, Takashi; Zingde, Surekha M.; Anscher, Mitchell S.; Bourhis, Jean; Begg, Adrian C.; Haustermans, Karin; Bentzen, Soren M.; Hendry, Jolyon H.

2005-01-01

Purpose: There is increasing interest in radiogenomics and the characterization of molecular profiles that predict normal tissue and tumor radioresponse. A meeting in Amsterdam was organized by the International Atomic Energy Agency to discuss this topic on an international basis. Methods and Materials: This report is not completely exhaustive, but highlights some of the ongoing studies and new initiatives being carried out worldwide in the banking of tumor and normal tissue samples underpinning the development of molecular marker profiles for predicting patient response to radiotherapy. It is generally considered that these profiles will more accurately define individual or group radiosensitivities compared with the nondefinitive findings from the previous era of cellular-based techniques. However, so far there are only a few robust reports of molecular markers predicting normal tissue or tumor response. Results: Many centers in different countries have initiated tissue and tumor banks to store samples from clinical trials for future molecular profiling analysis, to identify profiles that predict for radiotherapy response. The European Society for Therapeutic Radiology and Oncology GENEtic pathways for the Prediction of the effects of Irradiation (GENEPI) project, to store, document, and analyze sample characteristics vs. response, is the most comprehensive in this regard. Conclusions: The next 5-10 years are likely to see the results of these and other correlative studies, and promising associations of profiles with response should be validated in larger definitive trials

Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Presentations

International Nuclear Information System (INIS)

2012-01-01

The overall purpose of the Technical Meeting was to recognize and analyse the implications of the accident occurred at the Fukushima Dai-ichi Nuclear Power Station on current and future fast neutron systems design and operation. The aim was to provide a global forum for discussing the principal lessons learned from this event, and thus to review safety principles and characteristics of existing and future fast neutron concepts, especially in relation with extreme natural events which potentially may lead to severe accident scenarios. The participants also presented and discussed innovative technical solutions, design features and countermeasures for design extension conditions - including earthquakes, tsunami and other extreme natural hazards - which can enhance the safety level of existing and future fast neutron systems. Furthermore, the meeting gave the opportunity to present advanced methods for the evaluation of the robustness of plants against design extension conditions. Another important goal of this TM was to discuss how to harmonize safety approaches and goals for next generation’s fast reactors. Finally, the meeting was intended to identify areas where further research and development in nuclear safety, technology and engineering in the light of the Fukushima accident are needed. In the frame of the implementation of its Nuclear Safety Action Plan endorsed by all Member States, the IAEA will consider these areas as potential technical topics for new Coordinated Research Projects, to be launched in the near future

78 FR 49296 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2013-08-13

.... Greg Mann, Office of International and Interagency Relations, (202) 358-5140, NASA Headquarters... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-091] NASA International Space Station... meeting. SUMMARY: In accordance with the Federal Advisory Committee Act, Public Law 92-463, as amended...

75 FR 51852 - NASA International Space Station Advisory Committee; Meeting

Science.gov (United States)

2010-08-23

.... Donald Miller, Office of International and Interagency Relations, (202) 358-1527, National Aeronautics... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-090)] NASA International Space Station... meeting. SUMMARY: In accordance with the Federal Advisory Committee Act, Public Law 92-463, as amended...

76 FR 33700 - Board for International Food and Agricultural Development; Notice of Meeting

Science.gov (United States)

2011-06-09

... Citizenship and Public Affairs, Syracuse University. Board members with continuing service include Elsa Murano... International Food and Agricultural Development; Notice of Meeting Pursuant to the Federal Advisory Committee Act, notice is hereby given of the public meeting of the Board for International Food and Agricultural...

International cooperation in combating illicit trafficking of nuclear materials by technical means

International Nuclear Information System (INIS)

Herbillon, J; Koch, L; Mason, G; Niemeyer, S; Nikiforov, N

1999-01-01

A consensus has been emerging during the past several years that illicit trafficking of nuclear materials is a problem that needs a more focused international response. One possible component of a program to combat illicit trafficking is nuclear forensics whereby intercepted nuclear materials are analyzed to provide clues for answering attribution questions. In this report we focus on international cooperation that is specifically addressing the development of nuclear forensics. First we will describe the role of the Nuclear Smuggling International Technical Working Group (ITWG) in developing nuclear forensics, and then we will present some specific examples of cooperative work by the Institute for Transuranium Elements of the European Commission with various European states. Recognizing the potential importance of a nuclear forensics capability, the P-8 countries in 1995 encouraged technical experts to evaluate the role of nuclear forensics in combating nuclear smuggling and possibly developing mechanisms for international cooperation. As a result, an International Conference on Nuclear Smuggling Forensic Analysis was held in November, 1995, at Lawrence Livermore National Laboratory to investigate technical cooperation on nuclear forensics. The International Conference provided a unique mix of scientists, law enforcement, and intelligence experts from 14 countries and organizations. All participants were invited to make presentations, and the format of the Conference was designed to encourage open discussion and broad participation

Manager, Technology Services | IDRC - International Development ...

International Development Research Centre (IDRC) Digital Library (Canada)

The Manager, Technology Services (TS) manages IT operations and technical support. ... while ensuring high levels of customer service quality and availability. .... Represents the division and Centre during internal and external meetings, ...

Technical Memory 2008. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2011-01-01

The technical memory 2008 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialties by personnel of the mentioned institution during 2008. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management. [es

78 FR 16849 - Alaska Energy Authority; Notice of Dispute Resolution Panel Meeting and Technical Conference

Science.gov (United States)

2013-03-19

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14241-000] Alaska Energy Authority; Notice of Dispute Resolution Panel Meeting and Technical Conference On March 8, 2013, Commission staff, in response to the filing of a notice of [[Page 16850

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

BCI meeting 2005--workshop on technology: hardware and software.

Science.gov (United States)

Cincotti, Febo; Bianchi, Luigi; Birch, Gary; Guger, Christoph; Mellinger, Jürgen; Scherer, Reinhold; Schmidt, Robert N; Yáñez Suárez, Oscar; Schalk, Gerwin

2006-06-01

This paper describes the outcome of discussions held during the Third International BCI Meeting at a workshop to review and evaluate the current state of BCI-related hardware and software. Technical requirements and current technologies, standardization procedures and future trends are covered. The main conclusion was recognition of the need to focus technical requirements on the users' needs and the need for consistent standards in BCI research.

Meeting of Commission of International Committee on Petrology of Coals

Energy Technology Data Exchange (ETDEWEB)

Timofeev, P P; Bogolyubova, L I

1982-03-01

In Urbana, Illinois from 18-20 May 1979 the XXXII session of the International Committee on Petrology met. Reports were made on standards for the study of bituminous and anthracite coals. Use of reflective capacity of vitrain to determine coalification of coals was discussed along with a proposition to establish numerical boundaries between brown, bituminous and anthracite coals. The re-editing of the International Dictionary on Petrology of Coals was agreed upon in view of new facts on microcomponents of coal and methods of studying them. The next meeting of the Commission took place at Ostrav, Czechoslovakia from 14-26 April 1980. At the plenary session, new officials were elected and agreement to re-edit the Dictionary on Petrology of Coals was confirmed. At the meeting of the Commission on Coal Petrography the question of the determination of components of coal by quantitative diagnosis, and results of determining components of vitrain by measuring its reflective capacity were reported on. At the meeting of the Committee on Applying Facts of Petrology in Geology, the classification of solid oil bitumen and organic substance of sediments was discussed. At the meeting of the Committee on the Application of the Petrology of Coals in Industry, attention was given to discussing basic parameters for the international classification of coals to be presented at the meeting of the Economic Commission of Europe in Geneva. In the final plenary session of the commission, results of discussions were summarized. The next session was to be held in France in 1981. (In Russian)

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

77 FR 61583 - International Energy Agency Meetings

Science.gov (United States)

2012-10-10

...) will meet on October 17 and 18, 2012, at the headquarters of the IEA in Paris, France in connection... the International Energy Agency (IEA) will be held at the headquarters of the IEA, 9, rue de la F... October 18. The purpose of this notice is to permit attendance by representatives of U.S. company members...

Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24

Energy Technology Data Exchange (ETDEWEB)

Block, R.C.; Feiner, F. [American Nuclear Society, La Grange Park, IL (United States)

1995-09-01

Technical papers accepted for presentation at the Seventh International Topical Meeting on Nuclear Reactor Thermal-Hydraulics are included in the present Proceedings. Except for the invited papers in the plenary session, all other papers are contributed papers. The topics of the meeting encompass all major areas of nuclear thermal-hydraulics, including analytical and experimental works on the fundamental mechanisms of fluid flow and heat transfer, the development of advanced mathematical and numerical methods, and the application of advancements in the field in the development of novel reactor concepts. Because of the complex nature of nuclear reactors and power plants, several papers deal with the combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. The participation in the conference by the authors from several countries and four continents makes the Proceedings a comprehensive review of the recent progress in the field of nuclear reactor thermal-hydraulics worldwide. Individual papers have been cataloged separately.

Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24

International Nuclear Information System (INIS)

Block, R.C.; Feiner, F.

1995-09-01

Technical papers accepted for presentation at the Seventh International Topical Meeting on Nuclear Reactor Thermal-Hydraulics are included in the present Proceedings. Except for the invited papers in the plenary session, all other papers are contributed papers. The topics of the meeting encompass all major areas of nuclear thermal-hydraulics, including analytical and experimental works on the fundamental mechanisms of fluid flow and heat transfer, the development of advanced mathematical and numerical methods, and the application of advancements in the field in the development of novel reactor concepts. Because of the complex nature of nuclear reactors and power plants, several papers deal with the combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. The participation in the conference by the authors from several countries and four continents makes the Proceedings a comprehensive review of the recent progress in the field of nuclear reactor thermal-hydraulics worldwide. Individual papers have been cataloged separately

Historical Roots of International Biomedical and Health Informatics: The Road to IFIP-TC4 and IMIA through Cybernetic Medicine and the Elsinore Meetings.

Science.gov (United States)

Kulikowski, C A

2017-08-01

Background: It is 50 years since the International Federation of Information Processing (IFIP) Societies approved the formation of a new Technical Committee (TC) 4 on Medical Information Processing under the leadership of Professor Francois Grémy, which was the direct precursor of the International Medical Informatics Association (IMIA). Objectives: The goals of this paper are to give a very brief overview of early international developments leading to informatics in medicine, with the origins of the applications of computers to medicine in the USA and Europe, and two meetings - of the International Society of Cybernetic Medicine, and the Elsinore Meetings on Hospital Information Systems-that took place in 1966. These set the stage for the formation of IFIP-TC4 the following year, with later sponsorship of the first MEDINFO in 1974, setting the path for the evolution to IMIA. Methods: This paper reviews and analyzes some of the earliest research and publications, together with two critical contrasting meetings in 1966 involving international activities in what evolved into biomedical and health informatics in terms of their probable influence on the formation of IFIP-TC4. Conclusion: The formation of IFIP-TC 4 in 1967 by Francois Grémy arose out of his concerns for merging, at an international level, the diverse strands from the more abstract work on cybernetic medicine and its basis in biophysical and neural modeling, with the more concrete and health-oriented medical information processing that was developing at the time for hospitals and clinical decision-making. Georg Thieme Verlag KG Stuttgart.

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

A study on intensifying efficiency for international collaborative development of advanced nuclear energy technology

Energy Technology Data Exchange (ETDEWEB)

Lee, J. H.; Hahn, D. H.; Song, K. C.; Chang, J. H.; Kim, H. J.; Kim, H. J.; Lim, C. Y.; Lee, D. S.; Lee, Y. J. [KAERI, Daejeon (Korea, Republic of)

2011-03-15

The objective of the study was to participate the GIF for the efficient propulsion of future nuclear system development. For achieving the objective of this study, the followings were carried out. {Omicron} Analyze the international/domestic trends in the future nuclear energy system {Omicron} Analyze the domestic long-term R and D program for the future nuclear system and assist its implementation - Review the agenda of the executive committee, the technical committee, and sub-technical committee - Assist the committee meetings and workshops related to the future nuclear energy system {Omicron} Develop the participation strategy for the collaborative development of Gen-IV technology and conducting the international cooperation activities - Support the delegation by reviewing the agenda of GIF meetings in the technical and legal perspective - Research the system R and D arrangement and report its progress - Participate in the SFR SIA PA negotiation meeting and report its progress {Omicron} Support the activities related to I-NERI between Korea and U.S. - Support a delegation by reviewing the agenda in the technical/legal point of view - Participate in the BINERIC meetings and Support the related activities The result of this study may be used for 1) contribution to establishing the effective foundation and broadening the cooperation activities between the advanced countries and Korea and 2) contribution effective management of Gen IV international collaboration by technical/legal supporting

A study on intensifying efficiency for international collaborative development of advanced nuclear energy technology

International Nuclear Information System (INIS)

Lee, J. H.; Hahn, D. H.; Song, K. C.; Chang, J. H.; Kim, H. J.; Kim, H. J.; Lim, C. Y.; Lee, D. S.; Lee, Y. J.

2011-03-01

The objective of the study was to participate the GIF for the efficient propulsion of future nuclear system development. For achieving the objective of this study, the followings were carried out. Ο Analyze the international/domestic trends in the future nuclear energy system Ο Analyze the domestic long-term R and D program for the future nuclear system and assist its implementation - Review the agenda of the executive committee, the technical committee, and sub-technical committee - Assist the committee meetings and workshops related to the future nuclear energy system Ο Develop the participation strategy for the collaborative development of Gen-IV technology and conducting the international cooperation activities - Support the delegation by reviewing the agenda of GIF meetings in the technical and legal perspective - Research the system R and D arrangement and report its progress - Participate in the SFR SIA PA negotiation meeting and report its progress Ο Support the activities related to I-NERI between Korea and U.S. - Support a delegation by reviewing the agenda in the technical/legal point of view - Participate in the BINERIC meetings and Support the related activities The result of this study may be used for 1) contribution to establishing the effective foundation and broadening the cooperation activities between the advanced countries and Korea and 2) contribution effective management of Gen IV international collaboration by technical/legal supporting

Stockholm international conference 2003 on geological repositories: Political and technical progress

International Nuclear Information System (INIS)

2004-01-01

The conference reviewed global progress made as well as current perspectives on the activities to develop geologic repositories. The objectives were to review the progress in policy making as well as technical issues and to strengthen international co-operation on waste management and disposal issues. The first day of the conference addressed the policy aspects of geological repositories and the second day featured the more technical issues. Session 1: International progress in performing long-term safety studies and security of geological disposal were discussed and reviewed with examples from OECD/NEA, Belgium, Sweden, USA, Switzerland and Russia. Session 2: Views on stakeholder involvement and decision making process were presented by international organisations and national implementers from Japan, United Kingdom, Belgium and OECD/NEA. Session 3: Views on stakeholder involvement and decision making process were presented by regional and local stakeholders from France, Finland, Korea and Sweden. Session 4: International instruments assisting in the implementation of geological repositories were discussed, for example ICRP and IAEA/NEA safety documents, Joint Convention, Safeguard agreements, Nuclear Liability Conventions, etc. Session 5: The contribution of Research, Development and Demonstration was discussed with overviews of the progress achieved on scientific and technical issues over the past four years. Progress and key issues were presented from Switzerland, USA, Finland, Japan, Sweden and IAEA. Each of the papers and poster presentations have been analysed and indexed separately

Technical basis document for internal dosimetry

CERN Document Server

Hickman, D P

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosi...

IAEA technical meeting on atomic and plasma-material interaction data for fusion science technology. Summary report

International Nuclear Information System (INIS)

Clark, R.E.H.

2003-10-01

The proceedings and conclusions of the Technical Meeting on 'Atomic and Plasma- Material Interaction Data for Fusion Science Technology' held in Juelich, Germany on October 28-31 are summarized. During the course of the meetings working groups were formed to review the status of specific areas of atomic, molecular and material physics of relevance to fusion and to make recommendations on data needs in fusion from these areas. The reports of those working groups are summarized and the complete reports included as appendices. This meeting brought together over fifty leading scientists in fusion related data. Results of research in a number of topics were presented and very useful discussions were held. The meeting was extremely successful. (author)

Enchanted Clays: 44th Annual Meeting of the Clay Minerals Society (June 2007)

Energy Technology Data Exchange (ETDEWEB)

Randall T. Cygan

2007-06-01

“Enchanted Clays: 44th Annual Meeting of the Clay Minerals Society” was held in early June 2007 in beautiful and historic Santa Fe, New Mexico, USA. Santa Fe provided an idyllic location in the southwestern United States for the attendees to enjoy technical and social sessions while soaking up the diverse culture and wonderful climate of New Mexico—The Land of Enchantment. The meeting included a large and varied group of scientists, sharing knowledge and ideas, benefitting from technical interactions, and enjoying the wonderful historic and enchanted environs of Santa Fe. Including significant number of international scientists, the meeting was attended by approximately two hundred participants. The meeting included three days of technical sessions (oral and poster presentations), three days of field trips to clay and geological sites of northern New Mexico, and a full day workshop on the stabilization of carbon by clays. Details can be found at the meeting web site: www.sandia.gov/clay.

Synthesis of the expert group meetings convened as part of the substantive preparations for the International Conference on Population and Development.

Science.gov (United States)

1993-01-01

As part of the preparation for the 1994 International Conference on Population and Development to be sponsored by the UN in Cairo, 6 expert groups were convened to consider 1) population growth; 2) population policies and programs; 3) population, development, and the environment; 4) migration; 5) the status of women; and 6) family planning programs, health, and family well-being. Each group included 15 experts representing a full range of relevant scientific disciplines and geographic regions. Each meeting lasted 5 days and included a substantive background paper prepared by the Population Division as well as technical papers. Each meeting concluded with the drafting of between 18 and 37 recommendations (a total of 162). The meeting on population, the environment, and development focused on the implications of current trends in population and the environment for sustained economic growth and sustainable development. The meeting on population policies and programs observed that, since 1984, there has been a growing convergence of views about population growth among the nations of the world and that the stabilization of world population as soon as possible is now an internationally recognized goal. The group on population and women identified practical steps that agencies could take to empower women in order to achieve beneficial effects on health, population trends, and development. The meeting on FP, health, and family well-being reviewed policy-oriented issues emerging from the experience of FP programs. The meeting on population growth and development reviewed trends and prospects of population growth and age structure and their consequences for global sustainability. The population distribution and migration experts appraised current trends and their interrelationship with development. In nearly all of the group meetings, common issues emerged. Concern was universally voiced for sustainable development and sustained economic growth, relevance of past experience

75 FR 18507 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

Science.gov (United States)

2010-04-12

...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... guidance has been developed for veterinary use by the International Cooperation on Harmonisation of... associations to promote the international harmonization of regulatory requirements. FDA has participated in...

Neutron reflectometry: A probe for materials surfaces. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2006-01-01

Research reactors play an important role in delivering the benefits of nuclear science and technology. The IAEA, through its project on the effective utilization of research reactors, has been providing technical support to Member States and promotes activities related to specific applications. Neutron beam research is one of the main components in materials science studies. Neutron reflectometry is extremely useful for characterizing thin films and layered structures, polymers, oxide coatings on metals and biological membranes. The neutron has been a major probe for investigating magnetic materials. Development of magnetic multilayers is important for diverse applications in sensors, memory devices, etc. The special nature of the interaction of the neutron with matter makes it an important tool to locate low z elements in the presence of high z elements, which is useful in biology and polymer science. The role of neutron reflectometry in research and development in materials science and technology was discussed in a consultants meeting held in 2003. Following this, a technical meeting was organized from 16 to 20 August 2004 in Vienna to discuss the current status of neutron reflectometry, including the instrumentation, data acquisition, data analysis and applications. Experts in the field of neutron reflectometry presented their contributions, after which there was a brainstorming session on various aspects of the technique and its applications. This publication is the outcome of deliberations during the meeting and the presentations by the participants. This publication will be of use to scientists planning to develop a neutron reflectometer at research reactors. It will also help disseminate knowledge and information to material scientists, biologists and chemists working towards characterizing and developing new materials

Technical meeting on development of 'Deep Burn' concepts using coated particle fuel for incineration of nuclear waste, surplus fissile materials and plutonium without recourse to multiple reprocessing. Meeting report

International Nuclear Information System (INIS)

2013-01-01

Summary report of the technical meeting. The purpose of this meeting is to explore various Deep-Burn options and concepts being developed in Member States and to appraise the progress made towards the maturity of Deep-Burn concepts based on HTGR designs. The meeting will also identify technology development challenges towards the realization of Deep-Burn concepts and propose collaborative ways to address them

IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Working Material

International Nuclear Information System (INIS)

2013-01-01

In response to needs expressed by Member States and within a broader IAEA-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on Fast Reactor Data Knowledge Preservation (FRKP). The main objectives of the FRKP initiative are to: • Halt the on-going loss of information related to Fast Reactors (FR); • Collect, retrieve, preserve and make accessible already existing data and information on FR. These objectives require the implementation of activities supporting digital document archival, exchange, search and retrieval and facilitating, by developing and using suitable standards and IT tools, the knowledge preservation over the next decades. To this purpose the IAEA has developed the Fast Reactor Knowledge Organization System (FRKOS), a web-based application employing IAEA methodology and approach for categorization of FR knowledge domain, which allows creating a comprehensive and well-structured international inventory of fast reactor data and information provided by different Member States. The resulting Web Portal is established and maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems - which were presented and very well received during the recent IAEA Fast Reactor and Related Fuel Cycles Conference (FR13) - are supposed to be of interest for national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. The objectives of the technical meeting were to: • Exchange information between the member states/international organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • Present and discuss the member states’/international organizations’ policies and conditions for releasing to the IAEA both publicly

Technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'. Working material

International Nuclear Information System (INIS)

2003-01-01

In Liquid Metal cooled Fast Reactors (LMFR) or in accelerator driven sub-critical systems (ADS) with LMFR like sub-critical cores, the primary coolant pipes (PCP) connect the primary coolant pumps to the grid plate. A rupture in one of these pipes could cause significant loss of coolant flow to the core with severe consequences. In loop type reactors, all primary pipelines are provided with double envelopes and inter-space coolant leak monitoring systems that permit leak detection before break. Thus, the PCP rupture event can be placed in the beyond design basis event (BDBE) category. Such an arrangement is difficult to incorporate for pool type reactors, and hence it could be argued that the PCP rupture event needs to be analysed in detail as a design basis event (DBE, category 4 event). The primary coolant pipes are made of ductile austenitic stainless steel material and operate at temperatures of the cold pool and at comparatively low pressures. For such low stressed piping with negligible creep and embrittlement effects, it is of interest to discuss under what design provisions, for pool type reactors, the guillotine rupture of PCP could be placed in the BDBE category. The topical Technical Meeting (TM) on 'Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors' was called to enable the specialists to present the philosophy and analyses applied on this topic in the various Member States for different LMFRs. The scope of the Technical Meeting was to provide a global forum for information exchange on the philosophy applied in the various participating Member States and the analyses performed for different LMFRs with regard to the primary coolant pipe rupture event. More specifically, the objectives of the Technical Meeting were to review the safety philosophy for the PCP rupture event in pool type LMFR, to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to

Rice breeding with induced mutations II. Report of an FAO/IAEA research co-ordination meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1970-03-01

This report contains the proceedings of the fourth meeting of participants in the FAO/IAEA Co-ordinated Program of Research on the Use of Induced Mutations in Rice Breeding, a program which was initiated in 1964. The three previous meetings were reported as follows: First: proceedings published in the International Rice Commission Newsletter, Vol. XV, No. 1 (1966). Second: report presented to the IRC Working Party meeting at Lake Charles, Louisiana, 18-30 July 1966. Third: proceedings published by the IAEA as Technical Reports Series No. 86 under the title 'Rice breeding with induced mutations'. The fourth meeting was held at Oiso, Japan, on 12-14 August 1968. Co-operators from nine countries attended, together with scientists from five other countries, the International Rice Research Institute, the Rockefeller Foundation, the International Rice Commission, and the FAO and IAEA. In addition, a number of scientists from the host country were present. The purpose of the meeting was to present reports on research related to or carried out under the co-ordinated program in 1967/68, to review and co-ordinate research plans for 1968/69, and to draw up technical recommendations for future work.

Abstracts and papers of the 1997 International RERTR Meeting

International Nuclear Information System (INIS)

1997-10-01

The 1997 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was sponsored by the Argonne National Laboratory and was held in Jackson Hole, Wyoming, U.S.A. on 5-10 October 1997. The abstracts and available papers that were presented at this meeting are dealing with: National RERTR Programs; Fuel Development, Testing and Evaluation; Safety Tests and Evaluations; Core Conversion Studies; New LEU Reactors; Mo-99 Production From LEU Fission; Spent Fuel Management; Fuel Cycle issues

Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Working Material

International Nuclear Information System (INIS)

2012-01-01

The overall purpose of the Technical Meeting was to recognize and analyse the implications of the accident occurred at the Fukushima Dai-ichi Nuclear Power Station on current and future fast neutron systems design and operation. The aim was to provide a global forum for discussing the principal lessons learned from this event, and thus to review safety principles and characteristics of existing and future fast neutron concepts, especially in relation with extreme natural events which potentially may lead to severe accident scenarios. The participants also presented and discussed innovative technical solutions, design features and countermeasures for design extension conditions - including earthquakes, tsunami and other extreme natural hazards - which can enhance the safety level of existing and future fast neutron systems. Furthermore, the meeting gave the opportunity to present advanced methods for the evaluation of the robustness of plants against design extension conditions. Another important goal of this TM was to discuss how to harmonize safety approaches and goals for next generation’s fast reactors. Finally, the meeting was intended to identify areas where further research and development in nuclear safety, technology and engineering in the light of the Fukushima accident are needed. In the frame of the implementation of its Nuclear Safety Action Plan endorsed by all Member States, the IAEA will consider these areas as potential technical topics for new Coordinated Research Projects, to be launched in the near future

Summary report of consultants' meeting to review the requirements to improve and extend the IRDF library (International Reactor Dosimetry File (IRDF-2002))

International Nuclear Information System (INIS)

Greenwood, L.R.; Nichols, A.L.

2007-01-01

Presentations, recommendations and conclusions of a Consultants' Meeting to 'Review the Requirements to Improve and Extend the IRDF library (International Reactor Dosimetry File (IRDF-2002))' are summarized is this report. The main aims of this meeting were to discuss scientific and technical matters related to reactor dosimetry and to consider the needs for improvements to the existing data in IRDF-2002 and possible extensions to other higher neutron energy applications. Specific tasks were assigned and deadlines agreed. The requirements for fusion studies are particularly challenging (up to 60 MeV) and should include adequate covariance data - the provision of these neutron cross sections will require additional effort and assessment prior to initiating any work programme, and specific participants agreed to undertake preliminary exercises. (author)

Manual of engineering drawing technical product specification and documentation to British and international standards

CERN Document Server

Simmons, Colin H; Simmons, Colin

2012-01-01

Manual of Engineering Drawing is a comprehensive guide for experts and novices for producing engineering drawings and annotated 3D models that meet the recent BSI and ISO standards of technical product documentation and specifications. This fourth edition of the text has been updated in line with recent standard revisions and amendments. The book has been prepared for international use, and includes a comprehensive discussion of the fundamental differences between the ISO and ASME standards, as well as recent updates regarding legal components, such as copyright, patents, and other legal considerations. The text is applicable to CAD and manual drawing, and it covers the recent developments in 3D annotation and surface texture specifications. Its scope also covers the concepts of pictorial and orthographic projections, geometrical, dimensional and surface tolerancing, and the principle of duality. The text also presents numerous examples of hydraulic and electrical diagrams, applications, bearings, adhesives, ...

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.)

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.)

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.)

Summary report of IAEA technical meeting: 15. meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion

International Nuclear Information System (INIS)

Clark, R.E.H.; Peacock, N.J.

2007-02-01

The 15th Meeting of the Subcommittee on Atomic and Molecular Data for Fusion of the International Fusion Research Council was held on 20-21 April 2006, at the IAEA Headquarters in Vienna, Austria. Work of the Atomic and Molecular Data Unit for the period 2004-2006 was reviewed, and recommendations were made for the 2008-2009 budget cycle. The proceedings, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period June 2004 - March 2006, are also included. (author)

Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010'

International Nuclear Information System (INIS)

2007-01-01

ANS, ENS, AESJ and KNS are jointly organizing the 2007 International LWR Fuel Performance Meeting following the successful ENS TopFuel meeting held during 22-26 October, 2006 in Salamaca, Spain. Merging three premier nuclear fuel design and performance meetings: the ANS LWR Fuel Performance Meeting, the ENS TopFuel and Asian Water Reactor Fuel Performance Meeting (WRFPM) created this international meeting. The meeting will be held annually on a tri-annual rotational basis in USA, Asia, and Europe. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as performance experience in commercial and test reactors. The meeting excludes front end and back end fuel issues, however, it covers all front and/or back issues that impact fuel designs and performance

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.

American Telemedicine Association: 18th Annual International Meeting & Tradeshow

Directory of Open Access Journals (Sweden)

Benjamin Forstag

2012-12-01

Full Text Available For 18 years, the American Telemedicine Association (ATA Annual International Meeting & Exposition has been the premier forum for professionals in the telemedicine, telehealth and mHealth space -- one of the fastest growing meetings in the country. ATA 2013 is on course to be the largest ATA meeting ever, with over 6,000 projected attendees.  The program will include 500 educational sessions and posters, highlighting the latest innovations, applications and research in telemedicine. The 2013 exhibit hall will feature nearly 300 of the leading vendors in remote healthcare technologies. With over 6000 projected attendees, from all around the world, there's no better place to meet and network with your peers and thought leaders in the field. Detailed program information--including courses, sessions and CME information--will be available January 2013 at:http://www.americantelemed.org.

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.

Light Pollution - An international perspective

Science.gov (United States)

Wainscoat, Richard J.

2018-01-01

The CIE (Commission Internationale de l'Eclairage, or International Commission on Illumination) is the international organization devoted to worldwide cooperation and the exchange of information on all matters relating to the science and art of light and lighting, colour and vision, photobiology and image technology. Its actions and recommendations affect lighting worldwide, and artifiical lighitng has a profound impact on ground-based astronomy. The CIE establishes Technical Committees to research speicific aspects of lighting. The CIE will hold its biannual meeting in October 2017 in South Korea. I will report on astronomy and light pollution related information from that meeting.

Exploring the use of internal and externalcontrols for assessing microarray technical performance

Directory of Open Access Journals (Sweden)

Game Laurence

2010-12-01

Full Text Available Abstract Background The maturing of gene expression microarray technology and interest in the use of microarray-based applications for clinical and diagnostic applications calls for quantitative measures of quality. This manuscript presents a retrospective study characterizing several approaches to assess technical performance of microarray data measured on the Affymetrix GeneChip platform, including whole-array metrics and information from a standard mixture of external spike-in and endogenous internal controls. Spike-in controls were found to carry the same information about technical performance as whole-array metrics and endogenous "housekeeping" genes. These results support the use of spike-in controls as general tools for performance assessment across time, experimenters and array batches, suggesting that they have potential for comparison of microarray data generated across species using different technologies. Results A layered PCA modeling methodology that uses data from a number of classes of controls (spike-in hybridization, spike-in polyA+, internal RNA degradation, endogenous or "housekeeping genes" was used for the assessment of microarray data quality. The controls provide information on multiple stages of the experimental protocol (e.g., hybridization, RNA amplification. External spike-in, hybridization and RNA labeling controls provide information related to both assay and hybridization performance whereas internal endogenous controls provide quality information on the biological sample. We find that the variance of the data generated from the external and internal controls carries critical information about technical performance; the PCA dissection of this variance is consistent with whole-array quality assessment based on a number of quality assurance/quality control (QA/QC metrics. Conclusions These results provide support for the use of both external and internal RNA control data to assess the technical quality of microarray

Technical Report 2000; Memoria Tecnica 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The technical memory 2000 of the Nuclear Regulatory Authority (NRA) of the Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, safeguards and physical protection, and presented in congress or meetings of these specialities by personnel of the mentioned institution during 2000. In this edition the documents are presented on: Nuclear safety; Radiobiology; Occupational doses; Radiochemical; Environmental studies; Emergency plans; Radiation accidents; and International safeguards. Some of them are realized by agreements between the Nuclear Regulatory Authority of Argentina, universities and other national and international organizations.

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

76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

Science.gov (United States)

2011-04-14

... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

International RETRAN conference 1998: Proceedings

International Nuclear Information System (INIS)

Gose, G.; McFadden, J.

1998-09-01

The RETRAN computer code, developed by EPRI through its Contractors, EI International, Inc. (EI) and Computer Simulation and Analysis, Inc. (CSA), is now widely used by the international nuclear community for various types of safety analyses. In order to exchange information concerning the current use of the code by the various organizations, EPRI and CSA sponsored the Ninth International meeting in Monterey, California, on June 7--10, 1998. The opening session featured a panel discussion on Analysis Need for Supporting Nuclear Plants in the 21st Century by representatives of the US Nuclear Industry as well as a review of RETRAN activities since the last International RETRAN Meeting. During the three-day meeting, technical papers were presented by the various participants. The papers generally dealt with the following topics: (1) RETRAN-3D development, verification, and validation; (2) RETRAN-02/RETRAN-3D analysis of PWRs; (3) RETRAN-02/RETRAN-3D analysis of BWRs; and (4) CORETRAN development and analyses activities

4. International reservoir characterization technical conference

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This volume contains the Proceedings of the Fourth International Reservoir Characterization Technical Conference held March 2-4, 1997 in Houston, Texas. The theme for the conference was Advances in Reservoir Characterization for Effective Reservoir Management. On March 2, 1997, the DOE Class Workshop kicked off with tutorials by Dr. Steve Begg (BP Exploration) and Dr. Ganesh Thakur (Chevron). Tutorial presentations are not included in these Proceedings but may be available from the authors. The conference consisted of the following topics: data acquisition; reservoir modeling; scaling reservoir properties; and managing uncertainty. Selected papers have been processed separately for inclusion in the Energy Science and Technology database.

Meeting Report: The Twelfth International Mouse Genome Conference

Energy Technology Data Exchange (ETDEWEB)

Manolakou, Katerina; Cross, Sally H.; Simpson, Eleanor H.; Jackson, Ian J.

1998-10-01

The annual International Mouse Genome Conference (IMGC) is where, scientifically speaking, classical mouse genetics meets the relative newcomer of genomics. The 12th meeting took place last October in the delightful Bavarian village of Garmisch-Partenkirchen, and we were greeted by the sight on the mountains of the first snowfall of the season. However the discussions left little time for exploration. Minds of participants in Garmisch were focused by a recent document produced by the NIH and by discussions within other funding agencies worldwide. If implemented, the proposals will further enhance the status of the mouse as the principal model for study of the function of the human genome.

Behaviour of core internals. Proceedings of the IAEA specialists meeting. Working document

International Nuclear Information System (INIS)

1998-01-01

This meeting was organized by the IAEA within the framework of its International Working Group on Life Management of Nuclear Power Plants. It was held in Rez near Prague on the 6-8 October 1998. The purpose of the meeting was to provide an international forum for discussion on recent results in research and utility experience and to provide recommendations for future developments in NPP life management programmes. 12 papers were presented during 3 sessions. Individual abstracts have been prepared for each of the papers

Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-01-01

Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-01-01

Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

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

75 FR 19671 - International Standards on the Transport of Dangerous Goods; Public Meeting

Science.gov (United States)

2010-04-15

... (UNSCOE TDG) to be held June 21-30, 2010 in Geneva, Switzerland. During this meeting, PHMSA is also... international agenda. Information Regarding The UNSCOE TDG Meeting: DATES: Wednesday, June 9, 2010; 9:30 a.m.-12..., 2013. Topics on the agenda for the UNSCOE TDG meeting include: [cir] Explosives and related matters...

Accident Tolerant Fuel Concepts for Light Water Reactors. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2016-06-01

Nuclear fuel is a highly complex material that has been subject to continuous development over the past 40 years and has reached a stage where it can be safely and reliably irradiated up to 65 GWd/tU in commercial nuclear reactors. During this time, there have been many improvements to the original designs and materials used. However, the basic design of uranium oxide fuel pellets clad with zirconium alloy tubing has remained the fuel choice for the vast majority of commercial nuclear power plants. Severe accidents, such as those at the Three Mile Island and Fukushima Daiichi have shown that under such extreme conditions, nuclear fuel will fail and the high temperature reactions between zirconoi alloys and water will lead to the generation of hydrogen, with the potential for explosions to occur, daming the plant further. Recognizing that the current fuel designs are vulnerable to severe accident conditions, tehre is renewed interesst in alternative fuel designs that would be more resistant to fuel failure and hydrogen production. Such new fuel designs will need to be compatible with existing fuel and reactor systems if they are to be utilized in the current reactor fleet and in current new build designs, but there is also the possibility of new designs for new reactor systems. This publication provides a record of the Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, held at Oak Ridge National Laboratories (ORNL), United States of America, 13-16 October 2014, to consider the early stages of research and development into accident tolerant fuel. There were 45 participants from 10 countries taking part in the meeting, with 32 papers organized into 7 sessions, of which 27 are included in this publication. This meeting is part of a wider investigation into such designs, and it is anticipated that further Technical Meetings and research programmes will be undertaken in this field

77 FR 50516 - Fogarty International Center; Notice of Meetings

Science.gov (United States)

2012-08-21

... Board. The meeting will be open to the public as indicated below, with attendance limited to space... and the discussions could disclose confidential trade secrets or commercial property such as... Federal Domestic Assistance Program Nos. 93.106, Minority International Research Training Grant in the...

78 FR 50426 - Fogarty International Center; Notice of Meeting

Science.gov (United States)

2013-08-19

... meeting will be open to the public as indicated below, with attendance limited to space available... discussions could disclose confidential trade secrets or commercial property such as patentable materials, and... Assistance Program Nos. 93.106, Minority International Research Training Grant in the Biomedical and...

77 FR 1705 - Fogarty International Center; Notice of Meetings

Science.gov (United States)

2012-01-11

... meeting will be open to the public as indicated below, with attendance limited to space available... discussions could disclose confidential trade secrets or commercial property such as patentable materials, and... of Federal Domestic Assistance Program Nos. 93.106, Minority International Research Training Grant in...

Establishment of the International Power Institute. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Julius E. Coles

2000-08-04

The International Power Institute, in collaboration with American industries, seeks to address technical, political, economic and cultural issues of developing countries in the interest of facilitating profitable transactions in power related infrastructure projects. IPI works with universities, governments and commercial organizations to render project-specific recommendations for private-sector investment considerations. IPI also established the following goals: Facilitate electric power infrastructure transactions between developing countries and the US power industry; Collaborate with developing countries to identify development strategies to achieve energy stability; and Encourage market driven solutions and work collaboratively with other international trade energy, technology and banking organizations.

The Third International Meeting on Genetic Disorders in the RAS/MAPK Pathway: Toward a Therapeutic Approach

OpenAIRE

Korf, Bruce; Ahmadian, Reza; Allanson, Judith; Aoki, Yoko; Bakker, Annette; Wright, Emma Burkitt; Denger, Brian; Elgersma, Ype; Gelb, Bruce D.; Gripp, Karen W.; Kerr, Bronwyn; Kontaridis, Maria; Lazaro, Conxi; Linardic, Corinne; Lozano, Reymundo

2015-01-01

"The Third International Meeting on Genetic Disorders in the RAS/MAPK Pathway: Towards a Therapeutic Approach" was held at the Renaissance Orlando at SeaWorld Hotel (August 2-4, 2013). Seventy-one physicians and scientists attended the meeting, and parallel meetings were held by patient advocacy groups (CFC International, Costello Syndrome Family Network, NF Network and Noonan Syndrome Foundation). Parent and patient advocates opened the meeting with a panel discussion to set the stage regard...

June 1992 Hall B collaboation meeting

International Nuclear Information System (INIS)

Dennis, L.

1992-01-01

The Hall B collaboration meeting at the CEBAF 1992 Summer Workshop consisted of technical and physics working group meetings, a special beam line devices working group meeting the first meeting of the membership committee, a technical representatives meeting and a full collaboration meeting. Highlights of these meetings are presented in this report

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 on the IAEA technical meeting on application libraries for ADS and transmutation

International Nuclear Information System (INIS)

Stanculescu, S.; Trkov, A.

2004-12-01

Highlights of the technical meeting are given with respect to the source of evaluated nuclear data, codes for ADS analysis with associated application libraries, content of these libraries, and the procedure for producing them. Participants debated their requirements and formulated an action plan, with work divided between four sub-groups: review/analysis of ADS benchmarks; selection of evaluated nuclear data files; preparation of the cross-section libraries; and benchmarking. Specific tasks were assigned with deadlines. (author)

Twelfth annual meeting of the International Working Group on Fast Reactors. Summary report. Part I

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-05-01

The Twelfth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous AGM,in Vienna from 27 to 30 March 1979. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors.

Twelfth annual meeting of the International Working Group on Fast Reactors. Summary report. Part I

International Nuclear Information System (INIS)

1979-05-01

The Twelfth Annual Meeting of the IWGFR was held in accordance with the recommendation of the previous AGM,in Vienna from 27 to 30 March 1979. The meeting was attended by the Member States of the group: France, the Federal Republic of Germany, Italy, Japan, the United Kingdom, and the USA, as well as by representatives from CEC, IAEA and OECD and observer from the USSR. This document includes: review of the IWGFR Activities for the period since the Eleventh Annual Meeting of the Group; preliminary programme of international conference on breeder reactors as a world energy resource and the breeder fuel cycle; list of meetings on atomic energy which may be of interest to the IWGFR Members; IWGFR criteria for supporting some of the international conferences; list of proposed topics for the IWGFR Specialists' Meetings; list of topics for review articles on LMFBR recommended for publication by the IAEA; list of meetings sponsored by the IWGFR; a list of members of the International Working Group on Fast Reactors

76 FR 48939 - Announcement of Meeting of the International Telecommunication Advisory Committee

Science.gov (United States)

2011-08-09

... Street, NW., Washington, DC 20520, to seek advice from the telecommunications industry on: (a) The consultation of International Telecommunication Union, Telecommunication Standardization Sector Study Group 15... Telecommunication Advisory Committee SUMMARY: This notice announces a meeting of the International Telecommunication...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-02-01

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

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

International Nuclear Information System (INIS)

2000-02-01

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

Promotion of technical harmonisation on risk-based decision making

International Nuclear Information System (INIS)

Kirchsteiger, Christian; Cojazzi, Giacomo

2000-01-01

The EC-JRC International Workshop on Promotion of Technical Harmonisation on Risk-Based Decision Making, held at Stresa and Ispra, Italy, 22-25 May 2000, was an experts meeting to discuss the possible need of developing an internationally accepted generic 'standard' for risk-based decision making.This paper briefly describes the workshop background, its organisation and summarises its main results and conclusions; it reflects the personal opinions of the authors and in no way commits the European Commission. (author)

Status of international environmental remediation activities: A report from the Prague conference

International Nuclear Information System (INIS)

Slate, S.C.; Thornhill, C.K.; Allen, R.E.

1993-10-01

The Prague Conference on nuclear waste management and environmental remediation provided extensive interchange of ideas and insight into new technologies and management approaches throughout the world. A variety of environmental remediation technologies have potential application to Department of Energy facilities; others illustrate pitfalls to be avoided. This paper presents the highlights from the first environmental remediation (ER) technical program in the American Society of Mechanical Engineers' series of international nuclear waste management conferences. This program covers ER technologies, decontamination and decommissioning (D ampersand D) technologies and experience, ER site characterization and modeling, management of and results from actual clean up actions, and data on several major international environmental problems. Focusing on direct benefits to the Department of Energy's (DOE) ER Program, this paper summarizes pertinent technical information, identifies useful technical papers, lists key technical contacts, and identifies specific actions to obtain additional information. US attendance at meetings like this is normally quite limited compared to attendance at North American meetings. The purpose of this paper then is to increase general awareness of this meeting in US technical circles and to broadly disseminate key information to US ER programs and contractors. To do this, the paper is organized to present background information on the conference itself, document the beneficial technical information, and outline ongoing information exchange activities

77 FR 52784 - U.S. Department of State Advisory Committee on Private International Law: Notice of Annual Meeting

Science.gov (United States)

2012-08-30

... Choice of Court Agreements; international contract law; developments in major PIL organizations... International Law: Notice of Annual Meeting The Department of State's Advisory Committee on Private International Law (ACPIL) will hold its annual meeting on developments in private international law on Thursday...

A technical basis for meeting waste form stability requirements of 10 CFR 61

International Nuclear Information System (INIS)

Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

1988-01-01

To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

Abstracts and papers of the 2002 International RERTR Meeting

International Nuclear Information System (INIS)

2002-11-01

This 24th RERTR meeting has been organized in cooperation with the IAEA. It was attended by almost 200 participants coming from almost 30 different countries. Among them we have representatives from governmental and international organizations, private companies, reactor operators, fuel developers, regulators. The papers presented during following sessions: national and international RERTR programs, fuel development, manufacturing and qualification; fuel performance; HEU and LEU fuel cycle; LEU target development; licensing, safety and core assessment; reactor core conversion; acceptance program and spent fuel transportation; spent fuel management

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

Uncertainty Assessment for Theoretical Atomic and Molecular Scattering Data. Summary Report of a Joint IAEA-ITAMP Technical Meeting

International Nuclear Information System (INIS)

Chung, Hyun-Kyung; Bartschat, Klaus; Tennyson, Jonathan; Schultz, David R.

2014-10-01

This report summarizes the proceedings of the Joint IAEA-ITAMP Technical Meeting on “Uncertainty Assessment for Theoretical Atomic and Molecular Scattering Data” on 7-9 July 2014. Twenty-five participants from ten Member States and one from the IAEA attended the three-day meeting held at the Harvard-Smithsonian Center for Astrophysics in Cambridge, Massachusetts, USA and hosted by the Institute of Theoretical Atomic, Molecular and Optical Physics (ITAMP). The report includes discussions on the issues of uncertainty estimates for theoretical atomic and molecular scattering data. The abstracts of presentations presented in the meeting are attached in the Appendix. (author)

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

Science.gov (United States)

2011-08-19

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

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

INDC International Nuclear Data Committee

Energy Technology Data Exchange (ETDEWEB)

Nichols, A. [Univ. of Surrey, Guildford (United Kingdom); McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Dimitriou, P. [Intl Atomic Energy Agency (IAEA), Vienna (Austria)

2017-12-11

The 22nd meeting of the International Network of Nuclear Structure and Decay Data Evaluators was convened at the Lawrence Berkeley National Laboratory, Berkeley, USA, from 22 to 26 May 2017 under the auspices of the IAEA Nuclear Data Section. This meeting was attended by 38 scientists from 12 Member States and the IAEA, all of whom are concerned primarily with the measurement, evaluation and dissemination of nuclear structure and decay data. A summary of the meeting, data centre reports, various proposals considered, technical discussions, actions agreed by the participants, and the resulting recommendations/conclusions are presented within this document.

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

International Nuclear Information System (INIS)

Janev, R.K.

1999-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-12-01

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

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.

76 FR 6171 - U.S. Department of State Advisory Committee on Private International Law (ACPIL): Public Meeting...

Science.gov (United States)

2011-02-03

... International Law (ACPIL): Public Meeting on Family Law The Department of State, Office of Legal Adviser, Office of Private International Law would like to give notice of a public meeting to discuss preparations for the upcoming Special Commission of the Hague Conference on Private International Law on the 1980...

Proceedings of the fifth PTCOG meeting and international workshop on biomedical accelerators

Energy Technology Data Exchange (ETDEWEB)

1987-04-01

This volume contains the proceeding and individual papers presented at the Fifth PTCOG meeting and International Workshop on Biomedical Accelerators. The meeting was divided into sessions on the biomedical aspects of therapy delivery, new biomedical accelerators, facilities, and beam localization and status report. Individual papers have been abstracted and indexed for the Energy Data Base.

Proceedings of the fifth PTCOG meeting and international workshop on biomedical accelerators

International Nuclear Information System (INIS)

1987-04-01

This volume contains the proceeding and individual papers presented at the Fifth PTCOG meeting and International Workshop on Biomedical Accelerators. The meeting was divided into sessions on the biomedical aspects of therapy delivery, new biomedical accelerators, facilities, and beam localization and status report. Individual papers have been abstracted and indexed for the Energy Data Base

17th Meeting of the IFRC Subcommittee on Atomic and Molecular Data for Fusion. Summary Report of an IAEA Technical Meeting

International Nuclear Information System (INIS)

Braams, B.J.

2012-06-01

The 17th meeting of the Subcommittee on Atomic and Molecular Data of the International Fusion Research Council (IFRC) was held on 27-28 April 2010 at IAEA Headquarters in Vienna, Austria. Activities of the Atomic and Molecular Data Unit for the period 2006-2008 were reviewed, and recommendations were made for the 2010-2011 budget cycle. The proceedings, conclusions and recommendations of the Subcommittee meeting are briefly described in this report. Specific recommendations of the Subcommittee from this meeting, as well as the report on the activities of the IAEA Atomic and Molecular Data Unit for the period May 2006 - March 2008, are also included. (author)

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

Summary report of a technical meeting on covariances of nuclear reaction data: GANDR project

International Nuclear Information System (INIS)

Trkov, A.

2005-04-01

Highlights of the technical meeting are given with respect to the detailed study of the feasibility of creating a tool for the Global Assessment of Nuclear Data Requirements (GANDR) based on sensitivity and uncertainty analysis. GANDR was concluded to be fully practical on a modern computer of the desktop class. Participants debated their requirements and formulated recommendations and proposals for implementation. Specific tasks were assigned to participants with an estimated time for their execution. (author)

Exploring the Educational Value of Clinical Vignettes from the Society of General Internal Medicine National Meeting in the Internal Medicine Clerkship

Science.gov (United States)

Wofford, James L; Singh, Sonal

2006-01-01

INTRODUCTION Whether the clinical vignettes presented at the Society of General Internal Medicine (SGIM) annual meeting could be of educational value to third year students in the Internal Medicine clerkship has not been studied. OBJECTIVE To explore the relevance and learning value of clinical vignettes from the SGIM national meeting in the Internal Medicine clerkship. SETTING Third year Ambulatory Internal Medicine clerkship at one academic medical center (academic year 2005 to 2006). METHODS Students were introduced to the clinical vignette and oriented to the database of clinical vignettes available through the SGIM annual meeting website. Students then reviewed 5 to 10 clinical vignettes using a worksheet, and rated the learning value of each vignette using a 5-point Likert scale (1 = least, 5 = greatest). A single investigator evaluated congruence of the vignette with the Clerkship Directors of Internal Medicine (CDIM)-SGIM curriculum to assess relevance. MAIN RESULTS A total of 42 students evaluated 371 clinical vignettes from the 2004 and 2005 meetings. The clinical vignettes were curriculum-congruent in 42.6% (n = 175), and clearly incongruent in 40.4% (n = 164). The mean rating for learning value was 3.8 (±1.0) (5 signifying greatest learning value). Curriculum-congruent vignettes had a higher mean learning value compared with curriculum-incongruent vignettes (4.0 vs 3.6, Student's t-test, P =.017). CONCLUSION The clinical vignettes presented at the national SGIM meeting offer clinical content that is relevant and of some educational value for third year clerkship students. Based on this pilot study, the educational value and strategies for their use in the clinical clerkships deserve further study. PMID:17026730

Radiation treatment of gaseous and liquid effluents for contaminant removal. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-12-01

The Technical Meeting on Radiation Processing of Gaseous and Liquid Effluents conducted in Sofia, Bulgaria, 7-10 September 2004, discussed and evaluated issues related to the status and future trends in radiation application for environmental protection. Five experts from Bulgaria, India, the Republic of Korea, Poland, and the United States of America were invited to provide their experiences in this field. Twenty cost-free participants and observers - from Bulgaria, India, Lithuania, Poland and Ukraine -joined the meeting, and 15 papers in total were presented. Research and development in radiation processing of gaseous and liquid effluents is undertaken in three fields: electron beam flue gas treatment (SO x and NO x removal), wastewater purification and sewage sludge sterilization. Wastewater or sludge treatment and flue gas purification all differ from technological points of view, but they are common services and applications of environmental radiation technology applications, based mostly on electron accelerators. The technical meeting discussed new development in the field of radiation applications in environmental service, especially the status and prospects of radiation processing of gaseous and liquid effluents. Progress in the field of electron accelerators and gamma sources is crucial for routine application of the technology. Cost reduction and improvement of technical reliability are substantial especially for high power of accelerators and high activity of the sources needed for environmental applications. Environmental applications were carefully reviewed in accordance with the existing regulations and state of the art knowledge. The comparison with conventional commercial technologies was addressed as well. In flue gas treatment, applicability of the technology using different fossil fuels (coal, lignite, oil, etc.) was reviewed. The elaborated materials cover the technical and economical evaluation of the technologies. The possible applications of

Eleventh ITER negotiations meeting (N-11) and twelfth negotiators' standing sub-group meeting (NSSG-12)

International Nuclear Information System (INIS)

Luo Delong

2005-01-01

The Eleventh ITER Negotiations Meeting (N-11) and the Twelfth Negotiators' Standing Sub-Group (NSSG-12 convened on October 19-25, 2005 at the Kempinski Hotel Chengdu, Sichuan Province. China was the host of this meeting. Delegations from China, the European Union, Japan, the Republic of Korea, the Russian Federation and the United States of America, as well as members from the International Team, met there to continue their work to reach agreement on the joint implementation of the ITER international fusion energy R and D project. The delegations accepted the Vice Minister of Science and Technology, Mr. LIU Yanhua, and State Councillor, Mr. SHI Dinghuan as Moderators for N-11 and NSSG-12, respectively, and Mr. LUO Delong as Secretary for both meetings. At the Meeting, delegates discussed and made substantial progress on a full range of legal, technical, and administrative topics, including staffing for ITER, policies for managing the project and its procurements, and the continuing joint drafting of the agreement on establishing the international ITER Organization to implement the project. Delegates also explored the possibility of India joining the Negotiations. In the light of the reports presented to the Meeting from the recent joint exploratory mission to India, delegates identified a series of steps for the near future leading towards a possible agreement among all the Parties to India's accession. The Negotiations Meeting also discussed the progress report of NSSG and forward planning and future tasks. The Negotiators agreed that substantial progress was made on all topics, and delegations are optimistic that the Joint Implementation Agreement and related Annexes and instruments could be initialed in spring of 2006. As decided by all delegations, the next Twelfth ITER Negotiations Meeting will be held in Korea on 6 December, 2005

78 FR 70392 - Notice of Meeting of Advisory Committee on International Law

Science.gov (United States)

2013-11-25

... Law A meeting of the Department of State's Advisory Committee on International Law will take place on... Law School (Frederick Lawrence Student Conference Center), 2000 H Street NW., Washington, DC. Acting... Director, Advisory Committee on International Law, United States Department of State. [FR Doc. 2013-28232...

Special issue containing papers presented at the 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (7-11 September 2011) Special issue containing papers presented at the 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems (7-11 September 2011)

Science.gov (United States)

Berk, H. L.

2012-09-01

The topic of the behaviour of energetic alpha particles in magnetic fusion confined plasmas is perhaps the ultimate frontier plasma physics issue that needs to be understood in the quest to achieve controlled power from the fusion reaction in magnetically confined plasmas. The partial pressure of alpha particles in a burning plasma will be ~5-10% of the total pressure and under these conditions the alpha particles may be prone to develop instability through Alfvénic interaction. This may lead, even with moderate alpha particle loss, to a burn quench or severe wall damage. Alternatively, benign Alfvénic signals may allow the vital information to control a fusion burn. The significance of this issue has led to extensive international investigations and a biannual meeting that began in Kyiv in 1989, followed by subsequent meetings in Aspenäs (1991), Trieste (1993), Princeton (1995), JET/Abingdon (1997), Naka (1999), Gothenburg (2001), San Diego (2003), Takayama (2005), Kloster Seeon (2007) and Kyiv (2009). The meeting was initially entitled 'Alpha Particles in Fusion Research' and then was changed during the 1997 meeting to 'Energetic Particles in Magnetic Confinement Systems' in appreciation of the need to study the significance of the electron runaway, which can lead to the production of energetic electrons with energies that can even exceed the energy produced by fusion products. This special issue presents some of the mature interesting work that was reported at the 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems, which was held in Austin, Texas, USA (7-11 September 2011). This meeting immediately followed a related meeting, the 5th IAEA Technical Meeting on Theory of Plasma Wave Instabilities (5-7 September 2011). The meetings shared one day (7 September 2011) with presentations relevant to both groups. The presentations from most of the participants, as well as some preliminary versions of papers, are available at the

Signal processing and electronics for nuclear spectrometry. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2009-12-01

electronics and digital signal processing methods are enabling advances in numerous spectrometry applications such as lightweight, portable and hand held radiation instruments, and high-resolution digital medical imaging systems. The objective of this technical meeting was to review the current status, developments and trends in nuclear electronics and signal processing, and their application with various radiation detectors. The meeting discussed the problems faced and the solutions employed, to improve the performances of data acquisition systems and high-tech equipment used for nuclear spectrometry. Presentations made at the meeting elaborated operational experiences with modern signal processing and electronics, and highlighted the latest developments in this field. This publication summarizes the findings and conclusions arising from this technical meeting

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...

Internal design of technical systems under conditions of uncertainty

Energy Technology Data Exchange (ETDEWEB)

Krasnoshchekov, P S; Morozov, V V; Fedorov, V V

1982-03-01

An investigation is made of a model of internal design of a complex technical system in the presence of uncertain factors. The influence of an opponent on the design is examined. The concepts of hierarchical and balanced compatibility between the criteria of the designer, the opponent and the segregations functions are introduced and studied. The connection between the approach proposed and the methods of artificial intelligence is discussed. 5 references.

Applications of Research Reactors Towards Research on Materials for Nuclear Fusion Technology. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-11-01

of materials under development for Generation IV concepts. International collaboration among MTRs and specialized facilities has been identified as integral to progress in fusion development as well as enhancing reactor utilization. This publication specifies which areas of research remain in the qualification of structural materials and components, and has detailed the characteristics of many research reactors and devices that can accomplish an important portion of these necessary studies. This publication is the outcome of two recent IAEA sponsored meetings under its programme to enhance the utilization and collaboration of research reactor and material test facilities: - Consultancy meeting on Role of Research Reactors in Materials Research for Nuclear Fusion Technology, 13-15 December 2010, IAEA, Vienna; - Technical meeting on Materials under High Energy and High Intensity Neutron Fluxes for Nuclear Fusion Technology, 27-29 June 2011, IAEA, Vienna. These meetings brought together representatives from MTRs, spallation neutron sources, multiple beam irradiation facilities, material scientists as well as fusion community representatives to discuss the current state of fusion research and to plot necessary studies and modes of research collaboration

Clusters and Groups of Galaxies : International Meeting

CERN Document Server

Giuricin, G; Mezzetti, M

1984-01-01

The large-scale structure of the Universe and systems Clusters, and Groups of galaxies are topics like Superclusters, They fully justify the meeting on "Clusters of great interest. and Groups of Galaxies". The topics covered included the spatial distribution and the clustering of galaxies; the properties of Superclusters, Clusters and Groups of galaxies; radio and X-ray observations; the problem of unseen matter; theories concerning hierarchical clustering, pancakes, cluster and galaxy formation and evolution. The meeting was held at the International Center for Theoretical Physics in Trieste (Italy) from September 13 to September 16, 1983. It was attended by about 150 participants from 22 nations who presented 67 invited lectures (il) and contributed papers (cp), and 45 poster papers (pp). The Scientific Organizing Committee consisted of F. Bertola, P. Biermann, A. Cavaliere, N. Dallaporta, D. Gerba1, M. Hack, J . V . Peach, D. Sciama (Chairman), G. Setti, M. Tarenghi. We are particularly indebted to D. Scia...