2nd Karlsruhe International Summer School on Fusion Technologies

International Nuclear Information System (INIS)

Bahm, W.; Stycz, K.

2008-01-01

For the second time, the Karlsruhe Research enter together with European research institutions and industries invited young scientists and engineers to its ''International Summer School on Fusion Technologies.'' Fifty participants from all over Europe attended the lectures by 35 experts preesenting contributions from their areas of competence. Ten young scientists from India and another 10 from China were connected to the events by video link. Physics student Kornelia Stycz describes her impressions as a participant in the ''2 nd International Summer School on Fusion Technologies.'' (orig.)

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

International Nuclear Information System (INIS)

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

IAEA and IEA roles in international fusion energy research

International Nuclear Information System (INIS)

Dolan, T.; Nakamura, K.

2000-01-01

The article describes the IAEA's and the IEA's complementary roles in facilitating international fusion research cooperation. These roles represent highly desirable contributions to fusion research through pooling of limited human and financial resources. The two Agencies both coordinate research and organize technical meeting, but in different ways. They each have unique strengths and different modes of operation. In order to deal with potential overlaps and serve the fusion research community optimally, they are coordinating their activities

International research co-operation in the field of controlled thermonuclear fusion

International Nuclear Information System (INIS)

Conscience, J.-F.

2003-01-01

This final report for the Swiss Federal Office of Education and Science presents a review of activities carried out in 2002 within the framework of the International Experimental Thermonuclear Reactor (ITER) project that involves contributions from Canada, Japan, the Russian Federation and the European Union. Further agreements on the development of a fusion reactor with other countries, including Switzerland, the USA and China, are mentioned. The first chapter describes the current state of research on electricity production using nuclear fusion and discusses feasibility, safety, environmental, fuel supply and economic aspects. A second chapter reviews global efforts in the fusion area, including ITER and EURATOM projects and the activities running under the European Fusion Development Agreement EFDA and the JET Implementing Agreement. Finally, a third chapter deals with fusion research activities in Switzerland and the contributions made to international research by Swiss universities and institutes

International program activities in magnetic fusion energy

International Nuclear Information System (INIS)

1986-03-01

The following areas of our international activities in magnetic fusion are briefly described: (1) policy; (2) background; (3) strategy; (4) strategic considerations and concerns; (5) domestic program inplications, and (6) implementation. The current US activities are reviewed. Some of our present program needs are outlined

International bulletin on atomic and molecular data for fusion

International Nuclear Information System (INIS)

Stephens, J.A.; Bannister, M.E.; Fuhr, J.

1999-12-01

The International Bulletin on Atomic and Molecular Data for Fusion is prepared by the Atomic and Molecular Data Unit of the International Atomic Energy Agency. It is distributed free of charge by the IAEA to assist in the development of fusion research and technology. In part 1, the Atomic and Molecular Data Information System (AMDIS) is presented. In Part 2, the indexed papers are listed separately for structure and spectra, atomic and molecular collisions and surface interactions. Part 3 contains all the bibliographic data for both the indexed and non-indexed references. Finally, the Author Index (part 4) refers to the bibliographic references contained in part 3

The fourth international energy agency international workshop on beryllium technology for fusion

International Nuclear Information System (INIS)

Scaffidi-Argentina, F.; Longhurst, G.R.

2000-01-01

The main objective of the workshop was to support the advancement of the international development of fusion power through communication and dissemination of information on progress made in beryllium technology. This has been accomplished through presentation of original research on issues of current interest to the fusion beryllium community. The workshop was divided into ten technical sessions that addressed the following general topics: production and characterization, health and safety, forming and joining, chemical compatibility, thermal-mechanical properties, pebble bed behavior, high-heat-flux performance, irradiation effects, plasma-tritium interaction, and molten beryllium-bearing salts

The fourth international energy agency international workshop on beryllium technology for fusion

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Longhurst, G.R.

2000-05-01

The main objective of the workshop was to support the advancement of the international development of fusion power through communication and dissemination of information on progress made in beryllium technology. This has been accomplished through presentation of original research on issues of current interest to the fusion beryllium community. The workshop was divided into ten technical sessions that addressed the following general topics: production and characterization, health and safety, forming and joining, chemical compatibility, thermal-mechanical properties, pebble bed behavior, high-heat-flux performance, irradiation effects, plasma-tritium interaction, and molten beryllium-bearing salts.

Plasma Physics and Controlled Nuclear Fusion Research 1971. Vol. III. Proceedings of the Fourth International Conference on Plasma Physics and Controlled Nuclear Fusion Research

International Nuclear Information System (INIS)

1971-01-01

The ultimate goal of controlled nuclear fusion research is to make a new energy source available to mankind, a source that will be virtually unlimited and that gives promise of being environmentally cleaner than the sources currently exploited. This goal has stimulated research in plasma physics over the past two decades, leading to significant advances in the understanding of matter in its most common state as well as to progress in the confinement and heating of plasma. An indication of this progress is that in several countries considerable effort is being devoted to design studies of fusion reactors and to the technological problems that will be encountered in realizing these reactors. This range of research, from plasma physics to fusion reactor engineering, is shown in the present three-volume publication of the Proceedings of the Fourth Conference on Plasma Physics and Controlled Nuclear Fusion Research. The Conference was sponsored by the International Atomic Energy Agency and was held in Madison, Wisconsin, USA from 17 to 23 June 1971. The enthusiastic co-operation of the University of Wisconsin and of the United States Atomic Energy Commission in the organization of the Conference is gratefully acknowledged. The Conference was attended by over 500 scientists from 24 countries and 3 international organizations, and 143 papers were presented. These papers are published here in the original language; English translations of the Russian papers will be published in a Special Supplement to the journal Nuclear Fusion. The series of conferences on Plasma Physics and Controlled Nuclear Fusion Research has become a major international forum for the presentation and discussion of results in this important and challenging field. In addition to sponsoring these conferences, the International Atomic Energy Agency supports controlled nuclear fusion research by publishing the journal Nuclear Fusion, and has recently established an International Fusion Research Council

International collaboration in the development of materials for fusion

International Nuclear Information System (INIS)

Amelinckx, S.

1988-01-01

International collaboration in the field of fusion physics research has become a tradition since many years. There are good reasons for this. Fusion physics experiments require progressively larger and more expensive machines. The construction of a major fusion device is beyond the possibility of single nations, except for the largest ones. Moreover it is desirable to test several fundamentally different design options. It would therefore be unreasonable to duplicate major fusion physics experiments. The necessity to pool and coordinate efforts in this area has therefore been recognized since many years and not only within the European community, but even on a global scale. The situation is somewhat different in the area of fusion materials research. In a number of areas of materials research 'big machines' are not required and meaningful research is within the reach of even small countries, moreover it can be done in decentralized fashion. It should nevertheless be noted that the number of properties to be studied and the number of materials options to be evaluated is so extensive that even here excessive duplication would be harmful. (orig.)

Continuous internal channels formed in aluminum fusion welds

Science.gov (United States)

Gault, J.; Sabo, W.

1967-01-01

Process produces continuous internal channel systems on a repeatable basis in 2014-T6 aluminum. Standard machining forms the initial channel, which is filled with tungsten carbide powder. TIG machine fusion welding completes formation of the channel. Chem-mill techniques enlarge it to the desired size.

8th International School of Fusion Reactor Technology "Ettore Majorana"

CERN Document Server

Leotta, G G; Muon-catalyzed fusion and fusion with polarized nuclei

1988-01-01

The International School of Fusion Reactor Technology started its courses 15 years ago and since then has mantained a biennial pace. Generally, each course has developed the subject which was announced in advance at the closing of the previous course. The subject to which the present proceedings refer was chosen in violation of that rule so as to satisfy the recent and diffuse interest in cold fusion among the main European laboratories involved in controlled thermonuclear research (CTR). In the second half of 1986 we started to prepare a workshop aimed at assessing the state of the art and possibly of the perspectives of muon- catalyzed fusion. Research in this field has recently produced exciting experimental results open to important practical applications. We thought it worthwhile to consider also the beneficial effects and problems of the polarization ofthe nuclei in both cold and thermonuclear fusion. In preparing the 8th Course on Fusion Reactor Technology, it was necessary to abandon the tradi...

Review of the Strategic Plan for International Collaboration on Fusion Science and Technology Research. Fusion Energy Sciences Advisory Committee (FESAC)

International Nuclear Information System (INIS)

1998-01-01

The United States Government has employed international collaborations in magnetic fusion energy research since the program was declassified in 1958. These collaborations have been successful not only in producing high quality scientific results that have contributed to the advancement of fusion science and technology, they have also allowed us to highly leverage our funding. Thus, in the 1980s, when the funding situation made it necessary to reduce the technical breadth of the U.S. domestic program, these highly leveraged collaborations became key strategic elements of the U.S. program, allowing us to maintain some degree of technical breadth. With the recent, nearly complete declassification of inertial confinement fusion, the use of some international collaboration is expected to be introduced in the related inertial fusion energy research activities as well. The United States has been a leader in establishing and fostering collaborations that have involved scientific and technological exchanges, joint planning, and joint work at fusion facilities in the U.S. and worldwide. These collaborative efforts have proven mutually beneficial to the United States and our partners. International collaborations are a tool that allows us to meet fusion program goals in the most effective way possible. Working with highly qualified people from other countries and other cultures provides the collaborators with an opportunity to see problems from new and different perspectives, allows solutions to arise from the diversity of the participants, and promotes both collaboration and friendly competition. In short, it provides an exciting and stimulating environment resulting in a synergistic effect that is good for science and good for the people of the world.

Neutronics analysis of International Fusion Material Irradiation Facility (IFMIF). Japanese contributions

International Nuclear Information System (INIS)

Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki.

1997-10-01

In fusion reactor development for demonstration reactor, i.e., DEMO, materials tolerable for D-T neutron irradiation are absolutely required for both mechanical and safety point of views. For this requirement, several kinds of low activation materials were proposed. However, experimental data by actual D-T fusion neutron irradiation have not existed so far because of lack of fusion neutron irradiation facility, except fundamental radiation damage studies at very low neutron fluence. Therefore such a facility has been strongly requested. According to agreement of need for such a facility among the international parties, a conceptual design activity (CDA) of International Fusion Material Irradiation Facility (IFMIF) has been carried out under the frame work of the IEA-Implementing Agreement. In the activity, a neutronics analysis on irradiation field optimization in the IFMIF test cell was performed in three parties, Japan, US and EU. As the Japanese contribution, the present paper describes a neutron source term as well as incident deuteron beam angle optimization of two beam geometry, beam shape (foot print) optimization, and dpa, gas production and heating estimation inside various material loading Module, including a sensitivity analysis of source term uncertainty to the estimated irradiation parameters. (author)

International bulletin on atomic and molecular data for fusion. No. 59

International Nuclear Information System (INIS)

Stephens, J.A.; Bannister, M.E.; Fuhr, J.; Gilbody, H.B.

2001-03-01

The International Bulletin on Atomic and Molecular Data for Fusion is prepared by the Atomic and Molecular Data Unit of the International Atomic Energy Agency. It is distributed free of charge by the IAEA to assist in the development of fusion research and technology. In part 1, the Atomic and Molecular Data Information System (AMDIS) is presented. In Part 2, the indexed papers are listed separately for structure and spectra, atomic and molecular collisions and surface interactions. Part 3 contains all the bibliographic data for both the indexed and non-indexed references. Finally, the Author Index (part 4) refers to the bibliographic references contained in part 3

International bulletin on atomic and molecular data for fusion. No. 58

International Nuclear Information System (INIS)

Stephens, J.; Bannister, M.E.; Fuhr, J.; Gilbody, H.B.

2000-06-01

The International Bulletin on Atomic and Molecular Data for Fusion is prepared by the Atomic and Molecular Data Unit of the International Atomic Energy Agency. It is distributed free of charge by the IAEA to assist in the development of fusion research and technology. In part 1, the Atomic and Molecular Data Information System (AMDIS) is presented. In Part 2, the indexed papers are listed separately for structure and spectra, atomic and molecular collisions and surface interactions. Part 3 contains all the bibliographic data for both the indexed and non-indexed references. Finally, the Author Index (part 4) refers to the bibliographic references contained in part 3

ITER at the international conference on fusion reactor materials

International Nuclear Information System (INIS)

Kalinin, G.; Barabash, V.; Matera, R.

1998-01-01

The reports summarizes the topics of the eighth International Conference on Fusion Reactor Materials (ICFRM-8) which was held in Sendai, Japan, on 26-31 October 1997. The ICFRM is focused on the whole spectrum of materials and technologies to be applied in fusion reactors and related facilities. The total number of conference participants was over 500, representing 24 countries and about 600 oral and poster papers were presented at the conference. Three sessions were devoted to ITER materials: (i) Design-Materials Interface and ITER (oral session); (ii) ITER, Irradiation Facility and Technology, (poster session); (iii) ITER and Beyond (discussion session)

Sherwood Washburn's New physical anthropology: rejecting the "religion of taxonomy".

Science.gov (United States)

Mikels-Carrasco, Jessica

2012-01-01

Many physical anthropologists and nearly all of those studying primatology today can trace their academic genealogy to Sherwood Larned Washburn. His New physical anthropology, fully articulated in a 1951 paper, proposed that the study of hominid evolution must link understandings of form, function, and behavior along with the environment in order most accurately to reconstruct the evolution of our ancestors. This shift of concentration from strictly analyzing fossil remains to what Washburn termed adaptive complexes challenged not only Washburn's predecessors, but also led Washburn to critique the very system of academia within which he worked. Collaboration across multiple disciplines, linking the four fields of anthropology in order to understand humans and application of our understandings of human evolution to the betterment of society, are the hallmarks of Washburnian anthropology. In this paper I will explore how Washburn's New physical anthropology led him to not only change the research direction in physical anthropology, but also to challenge the academia within which he worked. I will conclude by reflecting on the prospects of continuing to practice Washburnian Anthropology.

1st International School of Fusion Reactor Technology "Ettore Majorana"

CERN Document Server

Knoepfel, Heinz; Safety, Environmental Impact and Economic Prospects of Nuclear Fusion

1990-01-01

This book contains the lectures and the concluding discussion of the "Seminar on Safety, Environmental Impact, and Economic Prospects of Nuclear Fusion", which was held at Erice, August 6-12, 1989. In selecting the contributions to this 9th meeting held by the International School of Fusion Reactor Technology at the E. Majorana Center for Scientific Cul­ ture in Erice, we tried to provide a comprehensive coverage of the many interre­ lated and interdisciplinary aspects of what ultimately turns out to be the global acceptance criteria of our society with respect to controlled nuclear fusion. Consequently, this edited collection of the papers presented should provide an overview of these issues. We thus hope that this book, with its extensive subject index, will also be of interest and help to nonfusion specialists and, in general, to those who from curiosity or by assignment are required to be informed on these as­ pects of fusion energy.

CONFERENCE DESCRIPTION Theory of Fusion Plasmas: Varenna-Lausanne International Workshop

Science.gov (United States)

Garbet, X.; Sauter, O.

2010-12-01

The Joint Varenna-Lausanne international workshop on Theory of Fusion Plasmas takes place every other year in a place particularly favourable for informal and in-depth discussions. Invited and contributed papers present state-of-the-art research in theoretical plasma physics, covering all domains relevant to fusion plasmas. This workshop always welcomes a fruitful mix of experienced researchers and students, to allow a better understanding of the key theoretical physics models and applications. Theoretical issues related to burning plasmas Anomalous Transport (Turbulence, Coherent Structures, Microinstabilities) RF Heating and Current Drive Macroinstabilities Plasma-Edge Physics and Divertors Fast particles instabilities Further details: http://Varenna-Lausanne.epfl.ch The conference is organized by: Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Fédérale de Lausanne, Association EURATOM - Confédération Suisse 'Piero Caldirola' International Centre for the Promotion of Science and International School of Plasma Physics Istituto di Fisica del Plasma del CNR, Milano Editors: X Garbet (CEA, Cadarache, France) and O Sauter (CRPP-EPFL, Lausanne, Switzerland)

International bulletin on atomic and molecular data for fusion. No. 11

International Nuclear Information System (INIS)

Katsonis, K.; Rumble, J. Jr.

1980-01-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains a list of references the publications on controlled fusion and plasma physics for 1979. It contains an index to the contributed papers presented at the 11th International Conference on the Physics of Electronics and Atomic Collision (ICPEAC) held in Kyoto (Japan) in summer 1979

Status and possible prospects of an international fusion materials irradiation facility

International Nuclear Information System (INIS)

Cozzani, F.

1999-01-01

Structural materials for future DT fusion power reactors will have to operate under intense neutron fields with energies up to 14 MeV and fluences in the order of 2 MW/m 2 per year. As environmental acceptability, safety considerations and economic viability will be ultimately the keys to the widespread introduction of fusion power, the development of radiation-resistant and low activation materials would contribute significantly to fusion development. For this purpose, testing of materials under irradiation conditions close to those expected in a fusion power station would require the availability, in an appropriate time framework, of an intense, high-energy neutron source. Recent advances in linear accelerator technology, in small specimens testing technology, and in the comprehension of damage phenomena, lead to the conclusion that an accelerator-based D-Li neutron source, with beam energy variability, would provide the most realistic option for a fusion materials testing facility. Under the auspices of the IEA, an international effort (EU, Japan, US, RF) to carry out the conceptual design activities (CDA) of an international fusion materials irradiation facility (IFMIF), based on the D-Li concept, have been carried out successfully. A final conceptual design report was produced at the end of 1996. A phase of conceptual design evaluation (CDE), presently underway, is extending and further refining some of the conceptual design details of IFMIF. The results indicate that an IFMIF-class installation would be technically feasible and could meet its mission objectives. However, a suitable phase of Engineering Validation, to carry out some complementary R and D and prototyping, would still be needed to resolve a few key technical uncertainties before the possibility to proceed toward detailed design and construction could be explored. (orig.)

Authors and Their ‘Mischievous’ Books: The Salutary Experience of Southey v Sherwood

Directory of Open Access Journals (Sweden)

Megan Richardson

2015-06-01

Full Text Available In the 1817 case of Southey v Sherwood Lord Eldon LC denied an injunction against the pirating of Robert Southey’s potentially ‘mischievous’ Wat Tyler, setting the tone for judgments in cases to come. The judges’ approach gave little account to the concerns of the authors whose interests in controlling their pirates lay in preserving their reputations and maintaining their livelihoods. The upshot was that the pirates prospered, large numbers of possibly seditious, blasphemous, defamatory and obscene books were published in England, and authors and judges were publicly excoriated. Eventually, judges had to reconsider their failed approach while authors looked for new ways to control their status and sources of income – as well as formulating some sharper distinctions between their public and private lives.

International research co-operation in the field of controlled thermonuclear fusion

International Nuclear Information System (INIS)

2004-01-01

This 26th report by the Swiss Federal Office for Education and Science presents a review of work done in Swiss institutes in 2003 as part of international research into thermonuclear fusion. A broad outline of the project and of its significance within the wider field of thermonuclear fusion research is given. This is followed by a review of the significant events in the world of fusion research, with emphasis placed on ITER and on the EURATOM fusion programme. A further chapter summarises events in Switzerland in 2003 and the report closes with a list of contacts for more information. Three annexes provide information on the current situation in fusion research, as well as scientific and technical highlights of the work performed in 2003 at the Plasma Physics Research Centre CRPP at the Federal Institute of Technology EPFL in Lausanne, Switzerland. Annex 3 reports on results obtained at the Physics Institute of the University of Basle. The annexes are for the benefit of the technically and scientifically versed reader, and brief summaries of them are given in the main body of the report

IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

International Nuclear Information System (INIS)

Rennich, M.J.

1995-12-01

Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops' as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems

Canada's Fusion Program

International Nuclear Information System (INIS)

Jackson, D. P.

1990-01-01

Canada's fusion strategy is based on developing specialized technologies in well-defined areas and supplying these technologies to international fusion projects. Two areas are specially emphasized in Canada: engineered fusion system technologies, and specific magnetic confinement and materials studies. The Canadian Fusion Fuels Technology Project focuses on the first of these areas. It tritium and fusion reactor fuel systems, remote maintenance and related safety studies. In the second area, the Centre Canadian de fusion magnetique operates the Tokamak de Varennes, the main magnetic fusion device in Canada. Both projects are partnerships linking the Government of Canada, represented by Atomic Energy of Canada Limited, and provincial governments, electrical utilities, universities and industry. Canada's program has extensive international links, through which it collaborates with the major world fusion programs, including participation in the International Thermonuclear Experimental Reactor project

Fusion energy 2000. Fusion energy 1998 (2001 Edition). Proceedings

International Nuclear Information System (INIS)

2001-01-01

This CD-ROM contains the Proceedings of 18th International Conference on Fusion Energy. It also contains an updated version of the Fusion Energy Conference 1998 Proceedings (38 additional papers included) as well as information on how to use this CD-ROM. The 18th International Atomic Energy Agency Fusion Energy Conference (FEC-2000) was held in Sorrento, Italy, 4-10 October 2000. 573 participants from over thirty countries and three international organizations took part in this Conference. The Conference was organized by the IAEA in co-operation with the Italian National Agency for New Technology, Energy and Environment (ENEA). Around 400 papers were presented in 22 oral and 8 poster sessions on magnetic confinement experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts, fusion technology, and safety and environment aspects. The 17th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations, was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology

UK's Brexit battle casts shadow over funding for international fusion projects

International Nuclear Information System (INIS)

Shepherd, John

2017-01-01

The ramifications of Brexit - the UK's decision to leave the European Union - have continued to send shockwaves through the nuclear energy community, since I explained in this column recently that the move also means withdrawing from the Euratom Treaty. Now the UK's divorce from the EU is posing a threat that could deal a major blow to international efforts in fusion research. In fact, confusing signals from the UK have cast doubt on future funding and support for two key areas of world fusion cooperation: the Oxfordshire-based Joint European Torus (Jet) programme and the International Thermonuclear Experimental Reactor (Iter) project at Cadarache in France.

UK's Brexit battle casts shadow over funding for international fusion projects

Energy Technology Data Exchange (ETDEWEB)

Shepherd, John [nuclear 24, Redditch (United Kingdom)

2017-04-15

The ramifications of Brexit - the UK's decision to leave the European Union - have continued to send shockwaves through the nuclear energy community, since I explained in this column recently that the move also means withdrawing from the Euratom Treaty. Now the UK's divorce from the EU is posing a threat that could deal a major blow to international efforts in fusion research. In fact, confusing signals from the UK have cast doubt on future funding and support for two key areas of world fusion cooperation: the Oxfordshire-based Joint European Torus (Jet) programme and the International Thermonuclear Experimental Reactor (Iter) project at Cadarache in France.

Combined development of international nuclear fusion test reactors

International Nuclear Information System (INIS)

Anon.

1987-01-01

Ambassadors of the four most important partners (Common Market, Japan, USA and USSR) in the IAEA sponsored INTOR project, met on the 15 and 16 March 1987 in Vienna under the auspices of the IAEA. A press release was issued acknowledging the considerable technical progress made in magnetic nuclear fusion research. Future design concepts, assistance in research and development work and other activities towards the provision of an international experimental thermonuclear reactor were discussed. (G.T.H.)

International Fusion Materials Irradiation Facility conceptual design activity. Present status and perspective

International Nuclear Information System (INIS)

Kondo, Tatsuo; Noda, Kenji; Oyama, Yukio

1998-01-01

For developing the materials for nuclear fusion reactors, it is indispensable to study on the neutron irradiation behavior under fusion reactor conditions, but there is not any high energy neutron irradiation facility that can simulate fusion reactor conditions at present. Therefore, the investigation of the IFMIF was begun jointly by Japan, USA, Europe and Russia following the initiative of IEA. The conceptual design activities were completed in 1997. As to the background and the course, the present status of the research on heavy irradiation and the testing means for fusion materials, the requirement and the technical basis of high energy neutron irradiation, and the international joint design activities are reported. The materials for fusion reactors are exposed to the neutron irradiation with the energy spectra up to 14 MeV. The requirements from the users that the IFMIF should satisfy, the demand of the tests for the materials of prototype and demonstration fusion reactors and the evaluation of the neutron field characteristics of the IFMIF are discussed. As to the conceptual design of the IFMIF, the whole constitution, the operational mode, accelerator system and target system are described. (K.I.)

Fusion reactor safety

International Nuclear Information System (INIS)

1987-12-01

Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

Argonne National Laboratory contributions to the International Symposium on Fusion Nuclear Technology (ISFNT)

Energy Technology Data Exchange (ETDEWEB)

1988-10-01

A total of sixteen papers with authors from Argonne National Laboratory were presented at the First International Symposium on Fusion Nuclear Technology (ISFNT), held in Tokyo, Japan, in April 1988. The papers cover the results of recent investigations in blanket design and analysis, fusion neutronics, materials experiments in liquid metal corrosion and solid breeders, tritium recovery analysis, experiments and analysis for liquid metal MHD, reactor safety and economic analysis, and transient electromagnetic analysis.

Argonne National Laboratory contributions to the International Symposium on Fusion Nuclear Technology (ISFNT)

International Nuclear Information System (INIS)

1988-10-01

A total of sixteen papers with authors from Argonne National Laboratory were presented at the First International Symposium on Fusion Nuclear Technology (ISFNT), held in Tokyo, Japan, in April 1988. The papers cover the results of recent investigations in blanket design and analysis, fusion neutronics, materials experiments in liquid metal corrosion and solid breeders, tritium recovery analysis, experiments and analysis for liquid metal MHD, reactor safety and economic analysis, and transient electromagnetic analysis

Cooperation Agreement. The text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization

International Nuclear Information System (INIS)

2009-01-01

The text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization is reproduced herein for the information of all Members. The Agreement entered into force on 13 October 2008 pursuant to Article 8

Cooperation Agreement. The Text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization

International Nuclear Information System (INIS)

2009-01-01

The text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization is reproduced herein for the information of all Members. The Agreement entered into force on 13 October 2008 pursuant to Article 8

Contributions to the third international symposium on fusion nuclear technologies (ISFNT-3)

International Nuclear Information System (INIS)

1994-11-01

The contributions of ENEA (Italian Agency for New Technologies, Energy and the Environment) Frascati center researchers to the 3rd international symposium on fusion nuclear technologies, held at Los Angeles, 27 June-1 July 1994, are presented

Application of internally cooled superconductors to tokamak fusion reactors

International Nuclear Information System (INIS)

Materna, P.A.

1986-01-01

Recent proposals for ignition tokamaks containing superconductors are reviewed. As the funding prospects for the U.S. fusion program have worsened, the proposed designs have been shrinking to smaller machines with less ambitious goals. The most recent proposal, the Tokamak Fusion Core Experiment (TFCX), was based on internally cooled cabled Nb 3 Sn conductors for the options which used superconductors. Internally cooled conductors are particularly advantageous in their electrical insulating properties and in the similarity of their winding procedures to those of conventional copper coils. Epoxy impregnation is possible and is advantageous both structurally and electrically. The allowable current density for this type of conductor was shown to be larger than the current density for more conventional superconducting technology. The TFCX effort identified research and development needed in advance of TFCX or any other large ignition machine. These topics include the metal used for the conduit; nuclear effects on materials; properties of electrical and thermal insulators; extension of superconducting technology to the sizes of coils envisioned and to the field level envisioned; pulsed coil superconducting technology; joints and insulating breaks in conductors; heat removal or flow path length limitations; mechanical behavior of potted conductor bundles; instrumentation; and fault modes and various questions integrated with overall machine design

Cooperation Agreement. The Text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization

International Nuclear Information System (INIS)

2009-01-01

The text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization is reproduced herein for the information of all Members. The Agreement entered into force on 13 October 2008 pursuant to Article 8 [fr

Cooperation Agreement. The Text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization

International Nuclear Information System (INIS)

2009-01-01

The text of the Cooperation Agreement between the International Atomic Energy Agency and the ITER International Fusion Energy Organization is reproduced herein for the information of all Members. The Agreement entered into force on 13 October 2008 pursuant to Article 8 [es

Assis, Machado de. Ressurrection by Machado de Assis. Trad. Karen Sherwood Sotelino. Pittsburgh: Latin American Literary Review Press, 2013. 162 p.

Directory of Open Access Journals (Sweden)

Cynthia Beatrice Costa

2015-12-01

Full Text Available Resenha crítica da primeira e única tradução para o inglês do romance machadiano Ressurreição, publicado em 1872. Lançada em 2013, a tradução da professora da Universidade de Stanford Karen Sherwood Sotelino chamou a atenção de estudiosos de Machado por mostrar como a obra do autor brasileiro desperta interesse atual no mundo anglófono.

Simulation of the time development of EBW emission from NSTX

Czech Academy of Sciences Publication Activity Database

Preinhaelter, Josef; Urban, Jakub; Taylor, G.; Diem, S.; Vahala, L.; Vahala, G.

2006-01-01

Roč. 51, č. 4 (2006), K1.00024 ISSN 0003-0503. [International Sherwood Fusion Theory Conference/2006./. Dallas, Texas , 22.4.2006-25.4.2006] Institutional research plan: CEZ:AV0Z20430508 Keywords : Conversion * Emission * Tokamaks * Electron Bernstein waves * Simulation * MAST * NSTX Subject RIV: BL - Plasma and Gas Discharge Physics http://www.aps.org/meet/APR06/baps/all_APR06.pdf http://meetings.aps.org/Meeting/APR06/Event/47670

The NIF: An international high energy density science and inertial fusion user facility

Directory of Open Access Journals (Sweden)

Moses E.I.

2013-11-01

Full Text Available The National Ignition Facility (NIF, a 1.8-MJ/500-TW Nd:Glass laser facility designed to study inertial confinement fusion (ICF and high-energy-density science (HEDS, is operational at Lawrence Livermore National Laboratory (LLNL. A primary goal of NIF is to create the conditions necessary to demonstrate laboratory-scale thermonuclear ignition and burn. NIF experiments in support of indirect-drive ignition began late in FY2009 as part of the National Ignition Campaign (NIC, an international effort to achieve fusion ignition in the laboratory. To date, all of the capabilities to conduct implosion experiments are in place with the goal of demonstrating ignition and developing a predictable fusion experimental platform in 2012. The results from experiments completed are encouraging for the near-term achievement of ignition. Capsule implosion experiments at energies up to 1.6 MJ have demonstrated laser energetics, radiation temperatures, and symmetry control that scale to ignition conditions. Of particular importance is the demonstration of peak hohlraum temperatures near 300 eV with overall backscatter less than 15%. Important national security and basic science experiments have also been conducted on NIF. Successful demonstration of ignition and net energy gain on NIF will be a major step towards demonstrating the feasibility of laser-driven Inertial Fusion Energy (IFE. This paper will describe the results achieved so far on the path toward ignition, the beginning of fundamental science experiments and the plans to transition NIF to an international user facility providing access to HEDS and fusion energy researchers around the world.

The NIF: An international high energy density science and inertial fusion user facility

Science.gov (United States)

Moses, E. I.; Storm, E.

2013-11-01

The National Ignition Facility (NIF), a 1.8-MJ/500-TW Nd:Glass laser facility designed to study inertial confinement fusion (ICF) and high-energy-density science (HEDS), is operational at Lawrence Livermore National Laboratory (LLNL). A primary goal of NIF is to create the conditions necessary to demonstrate laboratory-scale thermonuclear ignition and burn. NIF experiments in support of indirect-drive ignition began late in FY2009 as part of the National Ignition Campaign (NIC), an international effort to achieve fusion ignition in the laboratory. To date, all of the capabilities to conduct implosion experiments are in place with the goal of demonstrating ignition and developing a predictable fusion experimental platform in 2012. The results from experiments completed are encouraging for the near-term achievement of ignition. Capsule implosion experiments at energies up to 1.6 MJ have demonstrated laser energetics, radiation temperatures, and symmetry control that scale to ignition conditions. Of particular importance is the demonstration of peak hohlraum temperatures near 300 eV with overall backscatter less than 15%. Important national security and basic science experiments have also been conducted on NIF. Successful demonstration of ignition and net energy gain on NIF will be a major step towards demonstrating the feasibility of laser-driven Inertial Fusion Energy (IFE). This paper will describe the results achieved so far on the path toward ignition, the beginning of fundamental science experiments and the plans to transition NIF to an international user facility providing access to HEDS and fusion energy researchers around the world.

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

International Nuclear Information System (INIS)

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m 2 , 20 dpa/y in Fe, in a volume of 500 cm 3 and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

Summary of the fifth International Symposium on Fusion Nuclear Technology (ISFNT-5)

International Nuclear Information System (INIS)

Vetter, J.E.

1999-01-01

The fifth International Symposium on Fusion Nucler Technology was held in Rome on 19-24 September 1999. It was attended by about 350 participants from 17 countries. The main emphasis during this conference was given to developments in connection with ITER

PFMC-16. 16th international conference on plasma-facing materials and components for fusion applications. Abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-07-01

The performances of fusion devices and of future fusion power plants strongly depend on the plasma-facing materials and components. Resistance to heat and particle loads, compatibility in plasma operations, thermo-mechanical properties, as well as the response to neutron irradiation are critical parameters which need to be understood and tailored from atomistic to component levels. The 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications addresses these issues.

Proceedings of 1995 the first Taedok international fusion symposium on advanced tokamak researches

Energy Technology Data Exchange (ETDEWEB)

Kim, S K; Lee, K W; Hwang, C K; Hong, B G; Hong, G W [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-05-01

This proceeding is from the First Taeduk International Fusion Symposium on advanced tokamak research, which was held at Korea Atomic Energy Research Institute, Taeduk Science Town, Korea on March 28-29, 1995. (Author) .new.

Proceedings of 1995 the first Taedok international fusion symposium on advanced tokamak researches

International Nuclear Information System (INIS)

Kim, S. K.; Lee, K. W.; Hwang, C. K.; Hong, B. G.; Hong, G. W.

1995-05-01

This proceeding is from the First Taeduk International Fusion Symposium on advanced tokamak research, which was held at Korea Atomic Energy Research Institute, Taeduk Science Town, Korea on March 28-29, 1995. (Author) .new

The international thermonuclear experimental reactor and the future of nuclear fusion energy

International Nuclear Information System (INIS)

Pan Chuanhong

2010-01-01

Energy shortage and environmental problems are now the two largest challenges for human beings. Magnetic confinement nuclear fusion, which has achieved great progress since the 1990's, is anticipated to be a way to realize an ideal source of energy in the future because of its abundance, environmental compatibility, and zero carbon release. Exemplified by the construction of the International Thermonuclear Experimental Reactor (ITER), the development of nuclear fusion energy is now in its engineering phase, and should be realized by the middle of this century if all objectives of the ITER project are met. (author)

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D + )-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m 2 , 20 dpa/year for Fe) in a volume of 500 cm 3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m{sup 2}, 20 dpa/y in Fe, in a volume of 500 cm{sup 3} and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

Fusion Physics

Energy Technology Data Exchange (ETDEWEB)

Kikuchi, Mitsuru; Lackner, Karl; Tran, Minh Quang [eds.

2012-09-15

Recreating the energy production process of the Sun - nuclear fusion - on Earth in a controlled fashion is one of the greatest challenges of this century. If achieved at affordable costs, energy supply security would be greatly enhanced and environmental degradation from fossil fuels greatly diminished. Fusion Physics describes the last fifty years or so of physics and research in innovative technologies to achieve controlled thermonuclear fusion for energy production. The International Atomic Energy Agency (IAEA) has been involved since its establishment in 1957 in fusion research. It has been the driving force behind the biennial conferences on Plasma Physics and Controlled Thermonuclear Fusion, today known as the Fusion Energy Conference. Hosted by several Member States, this biennial conference provides a global forum for exchange of the latest achievements in fusion research against the backdrop of the requirements for a net energy producing fusion device and, eventually, a fusion power plant. The scientific and technological knowledge compiled during this series of conferences, as well as by the IAEA Nuclear Fusion journal, is immense and will surely continue to grow in the future. It has led to the establishment of the International Thermonuclear Experimental Reactor (ITER), which represents the biggest experiment in energy production ever envisaged by humankind.

Micromechanical and internal discontinuity aspects in fusion welded joints

International Nuclear Information System (INIS)

Nur Azida Che Lah; Aidy Ali

2009-01-01

Full text: This paper deals with characterization of macrostructure, microstructure, hardness, elemental compositions and internal discontinuities of ASTM A516 grade 70 fusion welded joints. The welded joints of ASTM A516 grade 70 carbon steel, which are widely used in pressure vessel fabrication were prepared using welding procedures of Manual Metal Arc (MMA), Metal Inert Gas (MIG) and Tungsten Inert Gas (TIG). Local microstructural condition and elemental composition of the welds were characterised using scanning electron microscopy (SEM) in association with energy dispersive X-ray (EDX). Radiography testing was applied to study the common internal weld defects. This comprehensive information provides a practical guide in order to determine the most adequate welding procedure and assisting in understanding the behaviour of the weld zones. (author)

International information exchange in fusion research

International Nuclear Information System (INIS)

Strickler, C.S.

1979-01-01

Formal and informal agreements exist between the US and several other countries, assuring the unrestricted exchange of magnetic fusion information. The Fusion Energy Library at Oak Ridge National Laboratory uses the US Department of Energy standard distribution system and exchange agreements to ensure the receipt of current reports. Selective dissemination of information, computer networks, and exchange programs are additional means for information gathering. The importance of these means as they relate to the fusion program in the US and specifically at ORNL is discussed

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

Fusion: introduction

International Nuclear Information System (INIS)

Decreton, M.

2006-01-01

The article gives an overview and introduction to the activities of SCK-CEN's research programme on fusion. The decision to construct the ITER international nuclear fusion experiment in Cadarache is highlighted. A summary of the Belgian contributions to fusion research is given with particular emphasis on studies of radiation effects on diagnostics systems, radiation effects on remote handling sensing systems, fusion waste management and socio-economic studies

Posterior Decompression, Lumber Interbody Fusion and Internal Fixation in the Treatment of Upper Lumbar Intervertebral Disc Herniation

Directory of Open Access Journals (Sweden)

DONG Zhan

2014-12-01

Full Text Available Objective: To assess the clinical outcomes of posterior decompression, interbody fusion and internal fixationfor the treatment of the upper lumbar intervertebral disc herniation. Methods: Twelve patients with the upper lumbar intervertebral disc herniation were treated by posterior decompression, interbosy fusion and internal fixation. The time of the operation, the amount of bleeding and the clinical efficacy were evaluated. Results: The time of operation was (143±36 min and the amount of bleeding during operation was (331.5±47.9 mL. There was no spinal cord and injuries, nerve injury, epidural damage and leakage of cerebrospinal fluid. All patients were followed up for 10～19 months with the average being 12.6 months. The functional scoring of Japanese Orthopedic Association (JOA before the operation was (11.4±3.3 scores and final score after follow-up was (22.9±3.1 scores and there were statistical difference (P＜0.01. Lumber interbody fusion of all patients completed successfully and the good rate after the operation was 91.7%. Conclusion: Posterior decompression, interbody fusion and internal fixation for the treatment of the upper lumbar intervertebral disc herniation was characterized by full exposure, safety and significant efficacy.

World progress toward fusion energy

International Nuclear Information System (INIS)

Davies, N.A.

1989-01-01

The author discusses international progress in fusion research during the last three years. Much of the technical progress has been achieved through international collaboration in magnetic fusion research. This progress has stimulated political interest in a multinational effort, aimed at designing and possibly constructing the world's first experimental fusion reactor. This interest was reflected in recent summit-level discussions involving President Mitterand, General Secretary Gorbachev, and President Reagan. Most recently, the European Community (EC), Japan, the United States, and the U.S.S.R. have decided to begin serious preparation for taking the next step toward practical fusion energy. These parties have agreed to begin the design and supporting R and D for an International Thermonuclear Experimental Reactor (ITER) under the auspices of the International Atomic Energy Agency (IAEA). The initiation of this international program to prepare for a fusion test reactor is discussed

Papers presented at the fourteenth international conference on plasma physics and controlled nuclear fusion research

International Nuclear Information System (INIS)

1994-01-01

This report contains the contributions of the CIEMAT's Fusion Unit to the 14th International Conference on Plasma Physics and Controlled Nuclear Fusion Research that was held by the International Atomic Energy Agency in Wurzburg, Germany from 30 September to 7 October 1992. Three papers were presented that summarized the main lines of work done in the Unit during the previous two years: The first one on the theoretical advances in the understanding of the Flexible Heliac TJ-II under construction, the second on the confinement studies performed in the operating TJ-I Tokamak and the third one on the description of the physical properties of the soon to be started TJ-IU Torsatron. (Author) 25 refs

Conference on Norwegian fusion research

International Nuclear Information System (INIS)

The question of instituting a systematic research programme in Norway on aspects of thermonuclear and plasma physics has been raised. The conference here reported was intended to provide basic information on the status of fusion research internationally and to discuss a possible Norwegian programme. The main contributions covered the present status of fusion research, international cooperation, fusion research in small countries and minor laboratories, fusion research in Denmark and Sweden, and a proposed fusion experiment in Bergen. (JIW)

10th International Conference and School on Plasma Physics and Controlled Fusion. Book of Abstracts

International Nuclear Information System (INIS)

Anon

2004-01-01

About 240 abstracts by Ukrainian and foreign authors submitted to 10-th International Conference and School on Plasma Physics and Controlled fusion have been considered by Conference Program Committee members. All the abstracts have been divided into 8 groups: magnetic confinement systems: stellarators, tokamaks, alternative conceptions; ITER and Fusion reactor aspects; basic plasma physics; space plasma; plasma dynamics and plasma-wall interaction; plasma electronics; low temperature plasma and plasma technologies; plasma diagnostics

5. IEA International workshop on beryllium technology for fusion. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The collection includes the abstracts of reports presented to the 5-th IEA international workshop on beryllium technology for fusion. The themes of reports are as follows: status of beryllium technology for fusion in Russia; manufacturing and testing of Be armoured first wall mock-up for ITER; development of the process of diffusion welding of metals stainless steel-copper-beryllium into a single composite; some features of beryllium-laser beam interaction; the effect of irradiation dose on tritium and helium release from neutron irradiated beryllium; thermal properties of neutron irradiated Be{sub 12}Ti. The results of investigating the mechanical properties variation and swelling of beryllium under high temperature neutron irradiation are presented.

5. IEA International workshop on beryllium technology for fusion. Book of abstracts

International Nuclear Information System (INIS)

2001-01-01

The collection includes the abstracts of reports presented to the 5-th IEA international workshop on beryllium technology for fusion. The themes of reports are as follows: status of beryllium technology for fusion in Russia; manufacturing and testing of Be armoured first wall mock-up for ITER; development of the process of diffusion welding of metals stainless steel-copper-beryllium into a single composite; some features of beryllium-laser beam interaction; the effect of irradiation dose on tritium and helium release from neutron irradiated beryllium; thermal properties of neutron irradiated Be 12 Ti. The results of investigating the mechanical properties variation and swelling of beryllium under high temperature neutron irradiation are presented [ru

End-stage hindfoot arthrosis: outcomes of tibiocalcaneal fusion using internal and Ilizarov fixation.

Science.gov (United States)

Crawford, Brooke; Watson, J Tracy; Jackman, James; Fissel, Brian; Karges, David E

2014-01-01

End-stage post-traumatic pantalar arthrosis from ankle, pilon, and talus fractures has often been complicated by infection, bone loss, and a soft tissue deficit. Patients can present with neuropathy, diabetes, tobacco use, and previously failed arthrodesis. Fusion in this population has been challenging, with nonunion rates up to 30%, often leading to amputation. We reviewed the results of a standardized protocol that combined simultaneous internal fixation with the Ilizarov technique to achieve fusion in high-risk patients. With institutional review board approval, a retrospective review of the patients treated with simultaneous internal fixation and an Ilizarov frame was undertaken. The records and radiographs allowed identification of the comorbidities and the presence or absence of successful fusion. Complications were acknowledged and treated. Fifteen patients had undergone the procedure. The mean follow-up period was 27.9 (range 9 to 67) months. Thirteen patients (86.67%) had had previous fusion failure. Twelve patients (80%) had developed post-traumatic arthrosis, 5 (33.33%) of whom had open injuries. All patients had 1 comorbidity, and 10 (66.67%) had multiple, including rheumatoid arthritis, diabetes (types 1 and 2), and smoking. Four patients (26.67%) presented with deep infection and bone loss. Union was achieved in 11 (73.33%), with 12 (80%) patients experiencing profound pain relief. Seven patients (46.67%) required symptomatic hardware removal. Three patients (20%) eventually underwent below-the-knee amputation for recalcitrant nonunion. Statistically significant correlations were found between smoking and wound infection and revision and between nonunion and amputation. Our results have indicated that combined internal fixation with Ilizarov application can provide a strong surgical option for the management of end-stage, pantalar arthritis. More studies are needed to compare the cohort outcomes and gait analysis in these patients with those who have

Assis, Machado de. Ressurrection by Machado de Assis. Trad. Karen Sherwood Sotelino. Pittsburgh: Latin American Literary Review Press, 2013. 162 p.

Directory of Open Access Journals (Sweden)

Cynthia Beatrice Costa

2015-05-01

Full Text Available http://dx.doi.org/10.5007/2175-7968.2015v35n2p494 Resenha crítica da primeira e única tradução para o inglês do romance machadiano Ressurreição, publicado em 1872. Lançada em 2013, a tradução da professora da Universidade de Stanford Karen Sherwood Sotelino chamou a atenção de estudiosos de Machado por mostrar como a obra do autor brasileiro desperta interesse atual no mundo anglófono.

Fusion technology: The Iter fusion experiment

International Nuclear Information System (INIS)

Dietz, K.J.

1994-01-01

Plans for the Iter international fusion experiment, in which the European Union, Japan, Canada, Russia, Sweden, Switzerland, and the USA cooperate, were begun in 1985, and construction work started in early 1994. These activities serve for the preparation of the design and construction documents for a research reactor in which a stable fusion plasma is to be generated. This is to be the basis for the construction of a fusion reactor for electricity generation. Preparatory work was performed in the Tokamak experiments with JET and TFTR. The fusion power of 1.5 GW will be attained, thus enabling Iter to keep a deuterium-tritium plasma burning. (orig.) [de

International bulletin on atomic and molecular data for fusion. No. 46

International Nuclear Information System (INIS)

Botero, J.

1993-06-01

The bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In Part I the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths; transition probabilities, oscillator strengths; interatomic potentials); (ii) atomic and molecular collisions (photon collisions; electron collisions; heavy-particle collisions; homonuclear sequences; isoelectronic sequences), and (iii) surface interactions (sputtering; chemical reactions; trapping and detrapping; surface damage; blistering, flaking; secondary electron emission). Part II contains the bibliographic data for the above listed topics and for high energy laser- and beam-matter interaction; interaction of atomic particles with fields. The atomic and molecular data needs in fusion research, as identified during the IAEA Consultants' Meeting on 'Atomic and Molecular Database for Hydrogen Recycling and Helium Exhaust from Fusion Reactors', June 1992, Vienna, are listed, covering (i) atomic and molecular collision processes, (ii) particle-surface interaction processes, and (iii) the status of data bases on atomic and molecular data and plasma-surface interactions. News on the ALADDIN (A labelled Atomic Data INterface) system is provided. Finally, a list of evaluated atomic and molecular data bases is provided

Contributions to the sixth international conference on fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-15

The ICFRM series has documented progress in the field of fusion reactor materials since the first conference held in Tokyo in 1984. The conference series has continually increased its coverage to the point where it now includes the comprehensive range of materials science and technology areas that enable systems designers to meet the needs of current experiments and to present innovative solutions for future energy systems. This publication contains five contributions to the sixth international conference which have each been indexed separately.

International bulletin on atomic and molecular data for fusion. No. 53

International Nuclear Information System (INIS)

Stephens, J.A.

1997-11-01

The International Bulletin on Atomic and Molecular Data for Fusion is presented in four parts: 1) The Atomic and Molecular Data Information System (AMDIS) of the IAEA; 2) the indexed papers listed separately for structure and spectra, atomic and molecular collisions, and surface interactions; 3) all bibliographic data for both the indexed and non-indexed references; 4) the Author Index refers to the bibliographic references contained in Part 3

Control of Internal Transport Barriers in Magnetically Confined Fusion Plasmas

Science.gov (United States)

Panta, Soma; Newman, David; Sanchez, Raul; Terry, Paul

2016-10-01

In magnetic confinement fusion devices the best performance often involves some sort of transport barriers to reduce the energy and particle flow from core to edge. Those barriers create gradients in the temperature and density profiles. If gradients in the profiles are too steep that can lead to instabilities and the system collapses. Control of these barriers is therefore an important challenge for fusion devices (burning plasmas). In this work we focus on the dynamics of internal transport barriers. Using a simple 7 field transport model, extensively used for barrier dynamics and control studies, we explore the use of RF heating to control the local gradients and therefore the growth rates and shearing rates for barrier initiation and control in self-heated fusion plasmas. Ion channel barriers can be formed in self-heated plasmas with some NBI heating but electron channel barriers are very sensitive. They can be formed in self-heated plasmas with additional auxiliary heating i.e. NBI and radio-frequency(RF). Using RF heating on both electrons and ions at proper locations, electron channel barriers along with ion channel barriers can be formed and removed demonstrating a control technique. Investigating the role of pellet injection in controlling the barriers is our next goal. Work supported by DOE Grant DE-FG02-04ER54741.

Coatings for fusion reactor environments

International Nuclear Information System (INIS)

Mattox, D.M.

1979-01-01

The internal surfaces of a tokamak fusion reactor control the impurity injection and gas recycling into the fusion plasma. Coating of internal surfaces may provide a desirable and possibly necessary design flexibility for achieving the temperatures, ion densities and containment times necessary for net energy production from fusion reactions to take place. In this paper the reactor environments seen by various componentare reviewed along with possible materials responses. Characteristics of coating-substrate systems, important to fusion applications, are delineated and the present status of coating development for fusion applications is reviewed. Coating development for fusion applications is just beginning and poses a unique and important challenge for materials development

Paramyxovirus F1 protein has two fusion peptides: implications for the mechanism of membrane fusion.

Science.gov (United States)

Peisajovich, S G; Samuel, O; Shai, Y

2000-03-10

Viral fusion proteins contain a highly hydrophobic segment, named the fusion peptide, which is thought to be responsible for the merging of the cellular and viral membranes. Paramyxoviruses are believed to contain a single fusion peptide at the N terminus of the F1 protein. However, here we identified an additional internal segment in the Sendai virus F1 protein (amino acids 214-226) highly homologous to the fusion peptides of HIV-1 and RSV. A synthetic peptide, which includes this region, was found to induce membrane fusion of large unilamellar vesicles, at concentrations where the known N-terminal fusion peptide is not effective. A scrambled peptide as well as several peptides from other regions of the F1 protein, which strongly bind to membranes, are not fusogenic. The functional and structural characterization of this active segment suggest that the F1 protein has an additional internal fusion peptide that could participate in the actual fusion event. The presence of homologous regions in other members of the same family suggests that the concerted action of two fusion peptides, one N-terminal and the other internal, is a general feature of paramyxoviruses. Copyright 2000 Academic Press.

Summary of the International Workshop on Magnetic Fusion Energy (MFE) Roadmapping in the ITER Era; 7–10 September 2011, Princeton, NJ, USA

International Nuclear Information System (INIS)

Neilson, G.H.; Federici, G.; Li, J.; Maisonnier, D.; Wolf, R.

2012-01-01

With the ITER project now well under way, the countries engaged in fusion research are planning, with renewed intensity, the research and major facilities needed to develop the science and technology for harnessing fusion energy. The Workshop on MFE Roadmapping in the ITER Era was organized to provide a timely forum for an international exchange of technical information and strategic perspectives on how best to tackle the remaining challenges leading to a magnetic fusion DEMO, a nuclear fusion device or devices with a level of physics and technology integration necessary to cover the essential elements of a commercial fusion power plant. Presentations addressed issues under four topics: (1) Perspectives on DEMO and the roadmap to DEMO; (2) Technology; (3) Physics-Technology integration and optimization; and (4) Major facilities on the path to DEMO. Participants identified a set of technical issues of high strategic importance, where the development strategy strongly influences the overall roadmap, and where there are divergent understandings in the world community, namely (1) the assumptions used in fusion design codes, (2) the strategy for fusion materials development, (3) the strategy for blanket development, (4) the strategy for plasma exhaust solution development and (5) the requirements and state of readiness for next-step facility options. It was concluded that there is a need to continue and to focus the international discussion concerning the scientific and technical issues that determine the fusion roadmap, and it was suggested that an international activity be organized under appropriate auspices to foster international cooperation on these issues. (conference report)

Proceedings of the sixth IEA international workshop on beryllium technology for fusion

Energy Technology Data Exchange (ETDEWEB)

Kawamura, Hiroshi [Japan Atomic Energy Research Inst., Kashiwa, Chiba (Japan); Tanaka, Satoru [Tokyo Univ., Tokyo (Japan); Ishitsuka, Etsuo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

2004-03-01

This report is the Proceedings of the Sixth International Energy Agency International Workshop on Beryllium Technology for Fusion. The workshop was held on December 2-5, 2003, at SEAGAIA in Miyazaki City, Japan with 69 participants who attended from Europe, the Russian Federation, Kazakhstan, Ukraine, China, the United States and Japan. The topics for papers were arranged into nine sessions; Status of beryllium study, Plasma and tritium interactions, ITER oriented issues, Neutron irradiation effects, Beryllide application, Disposal and recycling, Molten salt, Health and safety issues and Panel discussion. In the Panel discussion, the international collaboration for three topics, i.e., Neutron irradiation effects, Beryllide application, Recycling and Disposal, were discussed, and necessary items for the international collaboration were proposed. The 46 of the presented papers are indexed individually. (J.P.N.)

Contributions to the 7th International Conference on plasma surface interactions in controlled fusion devices

International Nuclear Information System (INIS)

1986-01-01

The report contains three papers presented in the 7th International Conference on plasma surface interactions in controlled fusion devices held in Princeton (USA) 5-9 May 1986, all referred to the FT Tokamak

Fusion energy and nuclear liability considerations

International Nuclear Information System (INIS)

Fork, William E.; Peterson, Charles H.

2014-01-01

For over 60 years, fusion energy has been recognised as a promising technology for safe, secure and environmentally-sustainable commercial electrical power generation. Over the past decade, research and development programmes across the globe have shown progress in developing critical underlying technologies. Approaches ranging from high-temperature plasma magnetic confinement fusion to inertial confinement fusion are increasingly better understood. As scientific research progresses in its aim to achieve fusion 'ignition', where nuclear fusion becomes self-sustaining, the international legal community should consider how fusion power technologies fit within the current nuclear liability legal framework. An understanding of the history of the civil nuclear liability regimes, along with the different risks associated with fusion power, will enable nations to consider the proper legal conditions needed to deploy and commercialise fusion technologies for civil power generation. This note is divided into three substantive parts. It first provides background regarding fusion power and describes the relatively limited risks of fusion technologies when compared with traditional nuclear fission technologies. It then describes the international nuclear liability regime and analyses how fusion power fits within the text of the three leading conventions. Finally, it examines how fusion power may fall within the international nuclear liability framework in the future, a discussion that includes possible amendments to the relevant international liability conventions. It concludes that the unique nature of the current civil nuclear liability regime points towards the development of a more tailored liability solution because of the reduced risks associated with fusion power. (authors)

Research into thermonuclear fusion

International Nuclear Information System (INIS)

Schumacher, U.

1989-01-01

The experimental and theoretical studies carried out in close international cooperation in the field of thermonuclear fusion by magnetic plasma confinement have achieved such progress towards higher plasma temperatures and densities, longer confinement times and, thus, increased fusion product, that emphasis now begins to be shifted from problems of physics to those of technology as a next major step is being prepared towards a large international project (ITER) to achieve thermonuclear burning. The generation and maintenance of a burning fusion plasma in an experimental physics phase will be followed by a phase of technical materials studies at high fluxes of fusion neutrons. These goals have been pursued since 1983 by an international study group at Garching working on the design of a Next European Torus (NET). Since May 1988, an international study group comprising ten experts each from the USSR, USA, Japan, and the European Community has begun to work on a design draft of ITER (International Thermonuclear Experimental Reactor) in Garching under the auspices of IAEA. (orig.) [de

How to improve the irradiation conditions for the International Fusion Materials Irradiation Facility

CERN Document Server

Daum, E

2000-01-01

The accelerator-based intense D-Li neutron source International Fusion Materials Irradiation Facility (IFMIF) provides very suitable irradiation conditions for fusion materials development with the attractive option of accelerated irradiations. Investigations show that a neutron moderator made of tungsten and placed in the IFMIF test cell can further improve the irradiation conditions. The moderator softens the IFMIF neutron spectrum by enhancing the fraction of low energy neutrons. For displacement damage, the ratio of point defects to cascades is more DEMO relevant and for tritium production in Li-based breeding ceramic materials it leads to a preferred production via the sup 6 Li(n,t) sup 4 He channel as it occurs in a DEMO breeding blanket.

Overview of international fusion technology programs

International Nuclear Information System (INIS)

Coffman, F.E.; Baublitz, J.E.; Beard, D.S.; Cohen, M.M.; Dalder, E.N.C.; Finfgeld, C.R.; Haas, G.M.; Head, C.R.; Murphy, M.R.; Nardella, G.R.

1979-01-01

World fusion technology programs, as well as current progress and future plans for the U.S., are discussed. Regarding conceptual design, the international INTOR tokamak study, the Garching Ignition Test Reactor Study, the U.S. Engineering Test Facility conceptual design, the Argonne National Laboratory Commercial Tokamak Study, mirror conceptual designs, and alternate concepts and applications studies are summarized. With regard to magnetics, progress to date in the large coil program and pulsed coil program is summarized. In the area of plasma heating and fueling and exhaust, work on a new positive ion source research and development program at Lawrence Berkeley Laboratory and Oak Ridge National Laboratory is described, as is negative ion work. Tradeoff considerations for radio-frequency heating alternatives are made, and a new 60-100 GHz electron cyclotron heating research and development program is discussed. Progress and plans for solid hydrogen pellet injector development are analyzed, as are plans for a divertor technology initiative. A brief review of the U.S. alternate applications and environment and safety program is included

International fusion materials irradiation facility and neutronic calculations for its test modules

International Nuclear Information System (INIS)

Sokcic-Kostic, M.

1997-01-01

The International Fusion Material Irradiation Facility (IFMIF) is a projected high intensity neutron source for material testing. Neutron transport calculations for the IFMIF project are performed for variety of here explained reasons. The results of MCNP neutronic calculations for IFMIF test modules with NaK and He cooled high flux test cells are presented in this paper. (author). 3 refs., 2 figs., 3 tabs

International fusion og spaltning

DEFF Research Database (Denmark)

Hansen, Lone L.

Bogen analyserer de nye muligheder fra 2007 i europæisk ret med hensyn til fusion eller spaltning mellem aktieselskaber og anpartsselskaber med hjemsted i forskellige europæiske lande. Bogen gennemgår de nye muligheder for strukturændringer, der herved er opstået mulighed for, og den sætter fokus...

Magnetic fusion reactor economics

International Nuclear Information System (INIS)

Krakowski, R.A.

1995-01-01

An almost primordial trend in the conversion and use of energy is an increased complexity and cost of conversion systems designed to utilize cheaper and more-abundant fuels; this trend is exemplified by the progression fossil fission → fusion. The present projections of the latter indicate that capital costs of the fusion ''burner'' far exceed any commensurate savings associated with the cheapest and most-abundant of fuels. These projections suggest competitive fusion power only if internal costs associate with the use of fossil or fission fuels emerge to make them either uneconomic, unacceptable, or both with respect to expensive fusion systems. This ''implementation-by-default'' plan for fusion is re-examined by identifying in general terms fusion power-plant embodiments that might compete favorably under conditions where internal costs (both economic and environmental) of fossil and/or fission are not as great as is needed to justify the contemporary vision for fusion power. Competitive fusion power in this context will require a significant broadening of an overly focused program to explore the physics and simbiotic technologies leading to more compact, simplified, and efficient plasma-confinement configurations that reside at the heart of an attractive fusion power plant

IFMIF [International Fusion Materials Irradiation Facility], an accelerator-based neutron source for fusion components irradiation testing: Materials testing capabilities

International Nuclear Information System (INIS)

Mann, F.M.

1988-08-01

The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>10/sup 15/ n/cm/sup 2/-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab

Decoupling internalization, acidification and phagosomal-endosomal/lysosomal fusion during phagocytosis of InlA coated beads in epithelial cells.

Directory of Open Access Journals (Sweden)

Craig D Blanchette

Full Text Available BACKGROUND: Phagocytosis has been extensively examined in 'professional' phagocytic cells using pH sensitive dyes. However, in many of the previous studies, a separation between the end of internalization, beginning of acidification and completion of phagosomal-endosomal/lysosomal fusion was not clearly established. In addition, very little work has been done to systematically examine phagosomal maturation in 'non-professional' phagocytic cells. Therefore, in this study, we developed a simple method to measure and decouple particle internalization, phagosomal acidification and phagosomal-endosomal/lysosomal fusion in Madin-Darby Canine Kidney (MDCK and Caco-2 epithelial cells. METHODOLOGY/PRINCIPAL FINDINGS: Our method was developed using a pathogen mimetic system consisting of polystyrene beads coated with Internalin A (InlA, a membrane surface protein from Listeria monocytogenes known to trigger receptor-mediated phagocytosis. We were able to independently measure the rates of internalization, phagosomal acidification and phagosomal-endosomal/lysosomal fusion in epithelial cells by combining the InlA-coated beads (InlA-beads with antibody quenching, a pH sensitive dye and an endosomal/lysosomal dye. By performing these independent measurements under identical experimental conditions, we were able to decouple the three processes and establish time scales for each. In a separate set of experiments, we exploited the phagosomal acidification process to demonstrate an additional, real-time method for tracking bead binding, internalization and phagosomal acidification. CONCLUSIONS/SIGNIFICANCE: Using this method, we found that the time scales for internalization, phagosomal acidification and phagosomal-endosomal/lysosomal fusion ranged from 23-32 min, 3-4 min and 74-120 min, respectively, for MDCK and Caco-2 epithelial cells. Both the static and real-time methods developed here are expected to be readily and broadly applicable, as they simply

International bulletin on atomic and molecular data for fusion. No. 42-45

International Nuclear Information System (INIS)

Botero, J.

1991-01-01

The bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In Part I the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths; transition probabilities, oscillator strengths; polarizabilities, electric moments; interatomic potentials); (ii) atomic and molecular collisions (photon collisions; electro collisions; heavy-particle collisions; homonuclear sequences), and (iii) surface interactions (sputtering; trapping, detrapping; adsorption, desorption; surface damage; blistering, flaking; chemical reactions). Part II contains the bibliographic data for the above listed topics and for plasma composition and impurities; plasma heating, cooling and fuelling; fusion research of general interest; high energy laser- and beam-matter interaction; interaction of atomic particles with fields. A list of evaluated data bases on atomic and molecular collisions and on particle-surface interactions is also given

Heavy ion fusion

International Nuclear Information System (INIS)

Bangerter, R.O.

1986-01-01

This report on the International Symposium on Heavy Ion Fusion held May 27-29, 1986 summarizes the problems and achievements in the areas of targets, accelerators, focussing, reactor studies, and system studies. The symposium participants recognize that there are large uncertainties in Heavy Ion Fusion but many of them are also optimistic that HIF may ultimately be the best approach to fusion

The FENIX [Fusion ENgineering International EXperimental] test facility

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Chaplin, M.R.; Miller, J.R.; Shen, S.S.; Summers, L.T.; Kerns, J.A.

1989-01-01

The Fusion ENgineering International EXperimental Magnet Facility (FENIX), under construction at Lawrence Livermore National Laboratory (LLNL), is a significant step forward in meeting the testing requirements necessary for the development of superconductor for large-scale, superconducting magnets. A 14-T, transverse field over a test volume of 150 x 60 x 150 mm in length will be capable of testing conductors the size of the International Thermonuclear Experimental Reactor (ITER). Proposed conductors for ITER measure ∼35 mm on one side and will operate at currents of up to 40 kA at fields of ∼14 T. The testing of conductors and associated components, such as joints, will require large-bore, high-field magnet facilities. FENIX is being constructed using the existing A 2o and A 2i magnets from the idle MFTF. The east and west A 2 pairs will be mounted together to form a split-pair solenoid. The pairs of magnets will be installed in a 4.0-m cryostat vessel located in the HFTF building at LLNL. Each magnet is enclosed in its own cryostat, the existing 4.0-m vessel serving only as a vacuum chamber. 4 refs., 8 figs

Hazard evaluation of The International Fusion Materials Irradiation Facility

Energy Technology Data Exchange (ETDEWEB)

Burgazzi, Luciano [ENEA-Centro Ricerche ' Ezio Clementel' , Advanced Physics Technology Division, Via Martiri di Monte Sole, 4, 40129 Bologna (Italy)]. E-mail: burgazzi@bologna.enea.it

2005-01-15

The International Fusion Materials Irradiation Facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for fusion. Liquid lithium is being circulated through a loop and is kept at a temperature above its freezing point. In the frame of the design phase called Key Element technology Phase (KEP), jointly performed by an international team to verify the most important risk factors, safety assessment of the whole plant has been required in order to identify the hazards associated with the plant operation. This paper discusses the safety assessments that were performed and their outcome: Failure Mode and Effect Analysis (FMEA) approach has been adopted in order to accomplish the task. Main conclusions of the study is that, on account of the safety and preventive measures adopted, potential plant related hazards are confined within the IFMIF security boundaries and great care must be exercised to protect workers and site personnel from operating the plant. The analysis has provided as a result a set of Postulated Initiating Events (PIEs), that is off-normal events, that could result in hazardous consequences for the plant, together with the total frequency and the list of component failures which could induce the PIE: this assures the exhaustive list of major initiating events of accident sequences, helpful to the further accident sequence analysis phase. Finally, for each one of the individuated PIEs, the evaluation of the accident evolution, in terms of effects on the plant and relative countermeasures, has allowed to verify that adequate measures are being taken both to prevent the accident occurrence and to cope with the accident consequences, thus assuring the fulfilment of the safety requirements.

PFMC14. 14th international conference on plasma-facing materials and components for fusion applications. Book of abstracts

International Nuclear Information System (INIS)

2013-01-01

The performance of fusion devices and of a future fusion power plant critically depends on the plasma facing materials and components. Resistance to local heat and particle loads, thermo-mechanical properties, as well as the response to neutron damage of the selected materials are critical parameters which need to be understood and tailored from atomistic to component levels. The 14th International Conference on Plasma-Facing Materials and Components for Fusion Applications addresses these issues. Among the topics of the joint conference recent developments and research results in the following fields are addressed: - Tungsten and tungsten alloys - Low-Z materials - Mixed materials - Erosion, redeposition and fuel retention - Materials under extreme thermal loads - Technology and testing of plasma-facing components - Neutron effects in plasma-facing materials - Advanced characterization of materials and components. Selected international speakers present overview lectures and treat detailed aspects of the given topics. Contributed papers to the subjects of the meeting are solicited for oral and poster presentations.

International bulletin on atomic and molecular data for fusion. No. 52

Energy Technology Data Exchange (ETDEWEB)

Stephens, J A [ed.

1997-08-01

This bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In part 1 the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths, transition probabilities, oscillator strengths, interatomic potentials); (ii) atomic and molecular collisions (photon collisions, electron collisions, heavy-particle collisions); and (iii) surface interactions (sputtering, chemical reactions, trapping and detrapping, adsorption, desorption, reflection, and secondary electron emission). Part 2 contains the bibliographic data, essentially for the above listed topics.

International bulletin on atomic and molecular data for fusion. No. 52

International Nuclear Information System (INIS)

Stephens, J.A.

1997-08-01

This bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In part 1 the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths, transition probabilities, oscillator strengths, interatomic potentials); (ii) atomic and molecular collisions (photon collisions, electron collisions, heavy-particle collisions); and (iii) surface interactions (sputtering, chemical reactions, trapping and detrapping, adsorption, desorption, reflection, and secondary electron emission). Part 2 contains the bibliographic data, essentially for the above listed topics

Fusion Canada issue 9

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-11-01

A short bulletin from the National Fusion Program. Included in this issue is a report on availability of Canadian Tritium, an ITER update, a CCFM update on Tokamak and the new team organization, an international report on Fusion in Canada and a Laser Fusion Project at the University of Toronto. 3 figs.

Fusion Canada issue 9

International Nuclear Information System (INIS)

1989-11-01

A short bulletin from the National Fusion Program. Included in this issue is a report on availability of Canadian Tritium, an ITER update, a CCFM update on Tokamak and the new team organization, an international report on Fusion in Canada and a Laser Fusion Project at the University of Toronto. 3 figs

Fusion in the energy system

DEFF Research Database (Denmark)

Fusion energy is the fundamental energy source of the Universe, as the energy of the Sun and the stars are produced by fusion of e.g. hydrogen to helium. Fusion energy research is a strongly international endeavor aiming at realizing fusion energy production in power plants on Earth. Reaching...... of integration into the future electricity system and socio-economic studies of fusion energy will be presented, referring to the programme of Socio-Economic Research on Fusion (SERF) under the European Fusion Energy Agreement (EFDA)....

Energy from inertial fusion

International Nuclear Information System (INIS)

1995-03-01

This book contains 22 articles on inertial fusion energy (IFE) research and development written in the framework of an international collaboration of authors under the guidance of an advisory group on inertial fusion energy set up in 1991 to advise the IAEA. It describes the actual scientific, engineering and technological developments in the field of inertial confinement fusion (ICF). It also identifies ways in which international co-operation in ICF could be stimulated. The book is intended for a large audience and provides an introduction to inertial fusion energy and an overview of the various technologies needed for IFE power plants to be developed. It contains chapters on (i) the fundamentals of IFE; (ii) inertial confinement target physics; (iii) IFE power plant design principles (requirements for power plant drivers, solid state laser drivers, gas laser drivers, heavy ion drivers, and light ion drivers, target fabrication and positioning, reaction chamber systems, power generation and conditioning and radiation control, materials management and target materials recovery), (iv) special design issues (radiation damage in structural materials, induced radioactivity, laser driver- reaction chamber interfaces, ion beam driver-reaction chamber interfaces), (v) inertial fusion energy development strategy, (vi) safety and environmental impact, (vii) economics and other figures of merit; (viii) other uses of inertial fusion (both those involving and not involving implosions); and (ix) international activities. Refs, figs and tabs

[International Panel on 14 MeV Intense Neutron Source Based on Accelerators for Fusion Materials Study

International Nuclear Information System (INIS)

Thoms, K.R.; Wiffen, F.W.

1991-01-01

Both travelers were members of a nine-person US delegation that participated in an international workshop on accelerator-based 14 MeV neutron sources for fusion materials research hosted by the University of Tokyo. Presentations made at the workshop reviewed the technology developed by the FMIT Project, advances in accelerator technology, and proposed concepts for neutron sources. One traveler then participated in the initial meeting of the IEA Working Group on High Energy, High Flux Neutron Sources in which efforts were begun to evaluate and compare proposed neutron sources; the Fourth FFTF/MOTA Experimenters' Workshop which covered planning and coordination of the US-Japan collaboration using the FFTF reactor to irradiate fusion reactor materials; and held discussions with several JAERI personnel on the US-Japan collaboration on fusion reactor materials

World progress toward fusion energy

International Nuclear Information System (INIS)

Clarke, J.F.

1989-09-01

This paper will describe the progress in fusion science and technology from a world perspective. The paper will cover the current technical status, including the understanding of fusion's economic, environmental, and safety characteristics. Fusion experiments are approaching the energy breakeven condition. An energy gain (Q) of 30 percent has been achieved in magnetic confinement experiments. In addition, temperatures required for an ignited plasma (Ti = 32 KeV) and energy confinements about 75 percent of that required for ignition have been achieved in separate experiments. Two major facilities have started the experimental campaign to extend these results and achieve or exceed Q = 1 plasma conditions by 1990. Inertial confinement fusion experiments are also approaching thermonuclear conditions and have achieved a compression factor 100-200 times liquid D-T. Because of this progress, the emphasis in fusion research is turning toward questions of engineering feasibility. Leaders of the major fusion R and D programs in the European Community (EC), Japan, the United States, and the U.S.S.R. have agreed on the major steps that are needed to reach the point at which a practical fusion system can be designed. The United States is preparing for an experiment to address the last unexplored scientific issue, the physics of an ignited plasma, during the late 1990's. The EC, Japan, U.S.S.R., and the United States have joined together under the auspices of the International Atomic Energy Agency (IAEA) to jointly design and prepare the validating R and D for an international facility, the International Thermonuclear Experimental Reactor (ITER), to address all the remaining scientific issues and to explore the engineering technology of fusion around the turn of the century. In addition, a network of international agreements have been concluded between these major parties and a number of smaller fusion programs, to cooperate on resolving a complete spectrum of fusion science and

Detailed facies analyses within the Bluell and Sherwood Members, Mission Canyon Formation, North Dakota, USA - Facies stacking patterns, sequence stratigraphy and porosity relationship, consequences for reservoir distribution

OpenAIRE

Sjöstedt, Tony

2017-01-01

Detailed core analysis from seven wells with cores cut within the overall carbonate succession that makes up the Bluell and Sherwood Members of the Mission Canyon Formation located in Renville County, North Dakota, resulted in the identification of eleven depositional facies. These facies that reflect a range in depositional conditions from inner to back ramp, that is shallow fair-weather to uppermost intertidal and supratidal conditions. Systematic core analysis using a highly detailed digit...

Accelerator conceptual design of the international fusion materials irradiation facility

International Nuclear Information System (INIS)

Sugimoto, M.; Kinsho, M.; Teplyakov, V.; Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J.; Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K.; Miyahara, A.; Olivier, M.; Piechowiak, E.; Tanabe, Y.

1998-01-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.)

Canadian fusion fuels technology project

International Nuclear Information System (INIS)

1986-01-01

The Canadian Fusion Fuels Technology Project was launched in 1982 to coordinate Canada's provision of fusion fuels technology to international fusion power development programs. The project has a mandate to extend and adapt existing Canadian tritium technologies for use in international fusion power development programs. 1985-86 represents the fourth year of the first five-year term of the Canadian Fusion Fuels Technology Project (CFFTP). This reporting period coincides with an increasing trend in global fusion R and D to direct more effort towards the management of tritium. This has resulted in an increased linking of CFFTP activities and objectives with those of facilities abroad. In this way there has been a continuing achievement resulting from CFFTP efforts to have cooperative R and D and service activities with organizations abroad. All of this is aided by the cooperative international atmosphere within the fusion community. This report summarizes our past year and provides some highlights of the upcoming year 1986/87, which is the final year of the first five-year phase of the program. AECL (representing the Federal Government), the Ministry of Energy (representing Ontario) and Ontario Hydro, have given formal indication of their intent to continue with a second five-year program. Plans for the second phase will continue to emphasize tritium technology and remote handling

Status report on controlled thermonuclear fusion

International Nuclear Information System (INIS)

1990-06-01

The International Fusion Research Council (IFRC), an advisory body to the International Atomic Energy Agency, reports on the current status of fusion; this report updates its 1978 status report. This report contains a General Overview and Executive Summary, and reports on all current approaches to fusion throughout the world; a series of technical reports is to be published elsewhere. This report is timely in that it not only shows progress which has occurred over the past, but interfaces with possible future devices, in particular the International Thermonuclear Experimental Reactor (ITER), whose conceptual design phase is nearing completion. 5 refs, 6 figs

Is there hope for fusion?

International Nuclear Information System (INIS)

Fowler, T.K.

1990-01-01

From the outset in the 1950's, fusion research has been motivated by environmental concerns as well as long-term fuel supply issues. Compared to fossil fuels both fusion and fission would produce essentially zero emissions to the atmosphere. Compared to fission, fusion reactors should offer high demonstrability of public protection from accidents and a substantial amelioration of the radioactive waste problem. Fusion still requires lengthy development, the earliest commercial deployment being likely to occur around 2025--2050. However, steady scientific progress is being made and there is a wide consensus that it is time to plan large-scale engineering development. A major international effort, called the International Thermonuclear Experimental Reactor (ITER), is being carried out under IAEA auspices to design the world's first fusion engineering test reactor, which could be constructed in the 1990's. 4 figs., 3 tabs

Status report on controlled thermonuclear fusion

International Nuclear Information System (INIS)

1990-01-01

The International Fusion Research Council has prepared this report on the current status of fusion, an update of its 1978 report, at the request of the Director General of the International Atomic Energy Agency. The report consists of an introductory note by the Director General, an Executive Summary and General Overview published in this document, and a series of technical reports. The background of fusion as an energy source is documented and compared with fission. The two approaches to thermonuclear fusion, magnetic confinement and inertial confinement, are discussed. The viability with respect to economic, environmental, and safety aspects is discussed. Fusion programs in the European Community, Japan, the USSR, the USA, as well as smaller programs in other countries are described. The status of fusion physics and technology is elucidated, and future directions and plans are indicated. 5 refs, 6 figs

Accelerator conceptual design of the international fusion materials irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, M.; Kinsho, M. [Japan Atomic Energy Res. Inst., Tokai, Ibaraki (Japan). Intense Neutron Source Lab.; Jameson, R.A.; Blind, B. [Los Alamos National Lab., NM (United States); Teplyakov, V. [Institute for High Energy Physics, Moscow (Russian Federation); Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J. [Northrop Grumman Corp., Bethpage, NY (United States); Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K. [Johann Wolfgang Goethe Univ., Frankfurt (Germany). Inst. fur Angewandte Phys.; Ferdinand, R.; Lagniel, J.-M. [CEA Saclay LNS, Gif-sur-Yvette (France); Miyahara, A. [Teikyo Univ., Tokyo (Japan); Olivier, M. [CEA DSM, Saclay, Gif-sur-Yvette (France); Piechowiak, E. [Northrop Grumman Corp., Baltimore, MD (United States); Tanabe, Y. [Toshiba Corp., Tsurumi-ku, Yokohama (Japan)

1998-10-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.) 8 refs.

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

2001-01-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Papers presented at the Fourteenth International conference on Plasma Physics and Controlled Nuclear Fusion Research. Organization International de la Energia Atomica Wuerzberg, Alemania 30 September - 7 October 1992

International Nuclear Information System (INIS)

1994-01-01

This report contains the contributions of the CIEMAT's Fusion Unit to the 14th International Conference on Plasma Physics and Controlled Nuclear Fusion Research that was held by the International Atomic Energy Agency in Wuerzberg, Germany from 30 September to 7 October 1992. Three papers were presented that summarized the, main lines of work done in the Unit during the previous two years: The first one on the theoretical advances in the understanding of the Fexible Heliac TJ-II under construction, the second on the confinement studies performed in the operating TJ-I Tokamak and the third one on the description of the physical properties of the soon to be started TJ-IU Torsatron. (Author) 25 refs

Bringing together fusion research

International Nuclear Information System (INIS)

Leiser, M.

1982-01-01

The increasing involvement of the IAEA in fusion, together with the growing efforts devoted to this area, are described. The author puts forward the idea that one of the most important aspects of this involvement is in providing a world-wide forum for scientists. The functions of the IFRC (International Fusion Research Council) as an advisory group are outlined, and the role played by IFRC in the definition and objectives of INTOR (International Tokamak Reactor) are briefly described

Establishment of an Institute for Fusion Studies

International Nuclear Information System (INIS)

Hazeltine, R.D.

1992-07-01

The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are: (1) to conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) to serve as a center for information exchange, nationally and internationally, by hosting exchange visits, conferences, and workshops; (3) and to train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. The theoretical research results that are obtained by the Institute contribute mainly to the progress of national and international efforts in nuclear fusion research, whose goal is the development of fusion power.as a basic energy source. In addition to its primary focus on fusion physics, the Institute is also involved with research in related fields, such as advanced computing techniques, nonlinear dynamics, plasma astrophysics, and accelerator physics. The work of EFS scientists continued to receive national and international recognition. Numerous invited papers were given during the past year at workshops, conferences, and scientific meetings. Last year IFS scientists published 95 scientific articles in technical journals and monographs

Fusion safety codes International modeling with MELCOR and ATHENA- INTRA

CERN Document Server

Marshall, T; Topilski, L; Merrill, B

2002-01-01

For a number of years, the world fusion safety community has been involved in benchmarking their safety analyses codes against experiment data to support regulatory approval of a next step fusion device. This paper discusses the benchmarking of two prominent fusion safety thermal-hydraulic computer codes. The MELCOR code was developed in the US for fission severe accident safety analyses and has been modified for fusion safety analyses. The ATHENA code is a multifluid version of the US-developed RELAP5 code that is also widely used for fusion safety analyses. The ENEA Fusion Division uses ATHENA in conjunction with the INTRA code for its safety analyses. The INTRA code was developed in Germany and predicts containment building pressures, temperatures and fluid flow. ENEA employs the French-developed ISAS system to couple ATHENA and INTRA. This paper provides a brief introduction of the MELCOR and ATHENA-INTRA codes and presents their modeling results for the following breaches of a water cooling line into the...

International bulletin on atomic and molecular data for fusion. Nos. 50-51

International Nuclear Information System (INIS)

Botero, J.; Stephens, J.A.

1996-10-01

This bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In part 1 the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths, transition probabilities, oscillator strengths, polarizabilities, electric moments, interatomic potentials); (ii) atomic and molecular collisions (photon collisions, electron collisions, heavy-particle collisions); and (iii) surface interactions (sputtering, chemical reactions, trapping and detrapping, adsorption, desorption, reflection, and secondary electron emission). Part 2 contains the bibliographic data, essentially for the above listed topics

Compact fusion reactors

CERN Multimedia

CERN. Geneva

2015-01-01

Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lawrenceville Plasma Physics and Lockheed Martin. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given.

West European magnetic confinement fusion research

International Nuclear Information System (INIS)

McKenney, B.L.; McGrain, M.; Hogan, J.T.; Porkolab, M.; Thomassen, K.I.

1990-01-01

This report presents a technical assessment and review of the West European program in magnetic confinement fusion by a panel of US scientists and engineers active in fusion research. Findings are based on the scientific and technical literature, on laboratory reports and preprints, and on the personal experiences and collaborations of the panel members. Concerned primarily with developments during the past 10 years, from 1979 to 1989, the report assesses West European fusion research in seven technical areas: tokamak experiments; magnetic confinement technology and engineering; fusion nuclear technology; alternate concepts; theory; fusion computations; and program organization. The main conclusion emerging from the analysis is that West European fusion research has attained a position of leadership in the international fusion program. This distinction reflects in large measure the remarkable achievements of the Joint European Torus (JET). However, West European fusion prominence extends beyond tokamak experimental physics: the program has demonstrated a breadth of skill in fusion science and technology that is not excelled in the international effort. It is expected that the West European primacy in central areas of confinement physics will be maintained or even increased during the early 1990s. The program's maturity and commitment kindle expectations of dramatic West European advances toward the fusion energy goal. For example, achievement of fusion breakeven is expected first in JET, before 1995

Plasma physics and controlled nuclear fusion research 1994. V. 3. Proceedings of the fifteenth international conference

International Nuclear Information System (INIS)

1996-01-01

This is the third volume of the proceedings of the 15th International Atomic Energy Agency Conference on Plasma Physics and Controlled Nuclear Fusion Research held in Seville, Spain, from 26 September - 1 October 1994. Contained in it are 29 papers on inertial confinement and 46 papers on magnetic confinement. Refs, figs, tabs

FENDL: International reference nuclear data library for fusion applications

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Ganesan, S.

1996-01-01

The IAEA nuclear data section, in co-operation with several national nuclear data centres and research groups, has created the first version of an internationally available fusion evaluated nuclear data library (FENDL-1). The FENDL library has been selected to serve as a comprehensive source of processed and tested nuclear data tailored to the requirements of the engineering design activity (EDA) of the ITER project and other fusion-related development projects. The present version of FENDL consists of the following sublibraries covering the necessary nuclear input for all physics and engineering aspects of the material development, design, operation and safety of the ITER project in its current EDA phase: FENDL/A-1.1: neutron activation cross-sections, selected from different available sources, for 636 nuclides, FENDL/D-1.0: nuclear decay data for 2900 nuclides in ENDF-6 format, FENDL/DS-1.0: neutron activation data for dosimetry by foil activation, FENDL/C-1.0: data for the fusion reactions D(d,n), D(d,p), T(d,n), T(t,2n), He-3(d,p) extracted from ENDF/B-6 and processed, FENDL/E-1.0:data for coupled neutron-photon transport calculations, including a data library for neutron interaction and photon production for 63 elements or isotopes, selected from ENDF/B-6, JENDL-3, or BROND-2, and a photon-atom interaction data library for 34 elements. The benchmark validation of FENDL-1 as required by the customer, i.e. the ITER team, is considered to be a task of high priority in the coming months. The well tested and validated nuclear data libraries in processed form of the FENDL-2 are expected to be ready by mid 1996 for use by the ITER team in the final phase of ITER EDA after extensive benchmarking and integral validation studies in the 1995-1996 period. The FENDL data files can be electronically transferred to users from the IAEA nuclear data section online system through INTERNET. A grand total of 54 (sub)directories with 845 files with total size of about 2 million

Proceedings: 2nd IEA international workshop on beryllium technology for fusion

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R.

1995-09-01

The 2nd IEA International Workshop on Beryllium Technology for Fusion was held September 6--8, 1995 at Jackson Lake Lodge, Wyoming. Forty-four participants took part in the workshop representing Europe, Japan, the Russian Federation, and the United States including representatives from both government laboratories and private industry. The workshop was divided into six technical sessions and a ``town meeting`` panel discussion. Technical sessions addressed the general topics of: Thermomechanical Properties; Manufacturing Technologies; Radiation Effects; Plasma/Tritium Interactions; Safety, Applications, and Design; and Joining and Testing. This volume contains the majority of the papers presented at the workshop. In some instances, the authors of the papers could not be present at the workshop, and the papers were given by others, sometimes in summary form and in some instances combined with others. The full papers are included here in the sequence in which they would have been given. In other instances, presentations were made but no papers were submitted for publication. Those papers do not appear here. In summary, the workshop was very successful. The main objectives of bringing key members of the fusion beryllium community together was certainly met. Forty-four participants registered, and 35 papers were presented. Individual papers are indexed separately on the energy data bases.

Proceedings: 2nd IEA international workshop on beryllium technology for fusion

International Nuclear Information System (INIS)

Longhurst, G.R.

1995-09-01

The 2nd IEA International Workshop on Beryllium Technology for Fusion was held September 6--8, 1995 at Jackson Lake Lodge, Wyoming. Forty-four participants took part in the workshop representing Europe, Japan, the Russian Federation, and the United States including representatives from both government laboratories and private industry. The workshop was divided into six technical sessions and a ''town meeting'' panel discussion. Technical sessions addressed the general topics of: Thermomechanical Properties; Manufacturing Technologies; Radiation Effects; Plasma/Tritium Interactions; Safety, Applications, and Design; and Joining and Testing. This volume contains the majority of the papers presented at the workshop. In some instances, the authors of the papers could not be present at the workshop, and the papers were given by others, sometimes in summary form and in some instances combined with others. The full papers are included here in the sequence in which they would have been given. In other instances, presentations were made but no papers were submitted for publication. Those papers do not appear here. In summary, the workshop was very successful. The main objectives of bringing key members of the fusion beryllium community together was certainly met. Forty-four participants registered, and 35 papers were presented. Individual papers are indexed separately on the energy data bases

FENIX [Fusion ENgineering International eXperimental]: A test facility for ITER [International Thermonuclear Experimental Reactor] and other new superconducting magnets

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Miller, J.R.

1990-01-01

The Fusion ENgineering International eXperimental (FENIX) Test Facility which is nearing completion at Lawrence Livermore National Laboratory, is a 76-t set of superconducting magnets housed in a 4-m-diameter cryostat. It represents a significant step toward meeting the testing needs for the development of superconductors appropriate for large-scale magnet applications such as the International Thermonuclear Experimental Reactor (ITER). The magnet set is configured to allow radial access to the 0.4-m-diameter high-field region where maximum fields up to 14 T will be provided. The facility is fitted with a thermally isolated test well with a port to the high-field region that allows insertion and removal of test conductors without disturbing the cryogenic environment of the magnets. It is expected that the facility will be made available to magnet developers internationally, and this paper discusses its general design features, its construction, and its capabilities

8th international workshop on plasma edge theory in fusion devices. Abstracts of invited and contributed papers

International Nuclear Information System (INIS)

Sipilae, S.K.; Heikkinen, J.A.

2001-01-01

The 8th International Workshop on Plasma Edge Theory in Fusion Devices, held at Dipoli Congress Centre, Espoo, Finland, is organised on behalf of the International Scientific Committee by Helsinki University of Technology and VTT (Technical Research Centre of Finland). Similar to the seven preceding Workshops, it addresses the theory for the boundary layer of magnetically confined fusion plasmas. It reflects the present status of the theory for the edge region of fusion plasmas. Emphasis is placed on the development of theory and of appropriate numerical methods as well as on self-consistent modelling of experimental data (including also empirical elements). The following topics are covered: basic edge plasma theory, models of special phenomena and edge control, and integrated edge plasma modelling. The International Scientific Committee has selected the papers and compiled the scientific programme. All other arrangements have been made by the Local Organising Committee. The Workshop is supported by the European Commission, High-Level Scientific Conferences. This Book of Abstracts contains the scientific programme and the abstracts of the invited and contributed papers. The Workshop has seven invited lectures of 60 minutes duration (including 10 minutes for discussion). In addition, 10 contributed papers were selected for oral presentation of 30 minutes duration (including five minutes for discussion). All oral presentations are given in plenary sessions. The remaining 34 contributed papers are presented as posters in three sessions. The invited lectures and contributed oral papers are presented also as posters. All invited and contributed papers will be refereed and published also as a regular issue of the journal Contributions to Plasma Physics. (orig.)

Nuclear fusion: The issues

International Nuclear Information System (INIS)

Griffin, R.D.

1993-01-01

The taming of fusion energy, has proved one of the most elusive quests of modern science. For four decades, the United States has doggedly pursued energy's holy grail, pumping more than $9 billion into research and reactor prototypes. This year, the federal government is slated to spend $339 million on fusion, more than the combined amount the government will spend for research on oil, natural gas, solar power, wind power, geothermal energy, biofuels and conservation. This article summarizes the technical, political in terms of international cooperation, economic, planning, etc. issues surrounding the continued development of fusion as a possible power source for the next century. Brief descriptions of how fusion works and of the design of a tokamak fusion machine are included

New trends in fusion research

CERN Multimedia

CERN. Geneva

2004-01-01

The efforts of the international fusion community aim at demonstrating the scientific feasibility of thermonuclear fusion energy power plants. Understanding the behavior of burning plasmas, i.e. plasmas with strong self-heating, represents a primary scientific challenge for fusion research and a new science frontier. Although integrated studies will only be possible, in new, dedicated experimental facilities, such as the International Tokamak Experimental Reactor (ITER), present devices can address specific issues in regimes relevant to burning plasmas. Among these are an improvement of plasma performance via a reduction of the energy and particle transport, an optimization of the path to ignition or to sustained burn using additional heating and a control of plasma-wall interaction and energy and particle exhaust. These lectures address recent advances in plasma science and technology that are relevant to the development of fusion energy. Mention will be made of the inertial confinement line of research, but...

Role of industry in international fusion program

International Nuclear Information System (INIS)

Durston, J.G.

1997-01-01

ITER combines a wide variety of technologies on an unprecedented scale of application. The experience of industry in design and integration of complex and advanced systems is helping to ensure that the engineering design of ITER is practicable and best meets the technical and cost objectives. The final development of fusion must take full benefit of the vast experience of industry in the management and coordination of major construction projects coupled with the fusion know-how being developed through participation in the ITER design activities. To achieve this, industry must be given an increasingly prominent role in the realization of the next-step device. The AE model provides an excellent means of achieving this aim. (author) 2 figs

Magnetic fusion and project ITER

International Nuclear Information System (INIS)

Park, H.K.

1992-01-01

It has already been demonstrated that our economics and international relationship are impacted by an energy crisis. For the continuing prosperity of the human race, a new and viable energy source must be developed within the next century. It is evident that the cost will be high and will require a long term commitment to achieve this goal due to a high degree of technological and scientific knowledge. Energy from the controlled nuclear fusion is a safe, competitive, and environmentally attractive but has not yet been completely conquered. Magnetic fusion is one of the most difficult technological challenges. In modem magnetic fusion devices, temperatures that are significantly higher than the temperatures of the sun have been achieved routinely and the successful generation of tens of million watts as a result of scientific break-even is expected from the deuterium and tritium experiment within the next few years. For the practical future fusion reactor, we need to develop reactor relevant materials and technologies. The international project called ''International Thermonuclear Experimental Reactor (ITER)'' will fulfill this need and the success of this project will provide the most attractive long-term energy source for mankind

Fusion and its future in Illinois

International Nuclear Information System (INIS)

Baker, C.C.

1984-08-01

This report was prepared by the Illinois Fusion Power Task Force under the sponsorship of the Governor's Commission on Sciences and Technology. The report presents the findings and recommendations of the Task Force, an explanation of the basic concepts of fusion, a summary of national and international programs and a description of ongoing fusion activities in Illinois

Invited and contributed papers presented by the theory group at the joint Varenna-Lausanne international workshop 'theory of fusion plasmas'

International Nuclear Information System (INIS)

1996-09-01

In this report eight invited and contributed papers of the theory group are included which were presented at joint Varenna-Lausanne international workshop on 'theory of fusion plasmas'. (author) figs., tabs., refs

The economic value of fusion energy

International Nuclear Information System (INIS)

Kim, S.H.; Clarke, J.; Edmonds, J.

1996-01-01

The potential economic benefit of fusion energy technology is significant and could dwarf the world's total expenditure on fusion energy research and development. However, the realization of these benefits will depend on the economic competitiveness of electricity generation from fusion energy technologies relative to that from other existing fossil fueled and renewable technologies, as well as the time in which fusion energy technologies are available for commercial operation. Utilizing the Second Generation Model, a long-term energy/economics model, the potential economic benefit of fusion energy technology for the United States was assessed. Model scenarios with hypothetical fusion power technologies based on the International Thermonuclear Experimental Reactor (ITER) design with varying cost and time of availability showed that significant economic benefit exists from a competitive fusion technology with cost of electricity (COE) of 0.06 $/kWhr and available in the year 2025. The fusion technology with these characteristics resulted in a total discounted GDP benefit of $105 billion from the year 1995 to 2100. On the other hand, uncompetitive fusion technologies with higher COE of 0.12 and 0.09 $/kWhr had little economic benefits. Moreover, delaying the introduction of all fusion technologies from 2025 to 2050 reduced the economic benefits of fusion technologies by more than 60 percent. Aside from the economic benefit of fusion technologies operating in the United States, the potential economic value of international trade in fusion technologies is likely to be even greater. If the United States could capture just a portion of the global electricity market, the export value of the fusion technology could amount to hundreds of billions of dollars, whereas the cost of importing the technology to the United States will erase any benefits derived from GDP increases

Fusion neutronics plan in the development of fusion reactor. With the aim of realizing electric power

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Hiroo; Morimoto, Yuichi; Ochiai, Kentarou; Sugimoto, Masayoshi; Nishitani, Takeo; Takeuchi, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2000-10-01

On June 1992, Atomic Energy Commission in Japan has settled Third Phase Program of Fusion Research and Development to achieve self-ignition condition, to realize long pulse burning plasma and to establish basis of fusion engineering for demonstration reactor. This report describes research plan of Fusion Neutron Laboratory in JAERI toward a development of fusion reactor with an aim of realizing electric power. The fusion neutron laboratory has a fusion neutronics facility (FNS), intense fusion neutron source. The plan includes research items in the FNS; characteristics of shielding and breeding materials, nuclear characteristics of materials, fundamental irradiation process of insulator, diagnostics materials and structural materials, and development of in-vessel diagnostic technology. Upgrade of the FNS is also described. Also, the International Fusion Material Irradiation Facility (IFMIF) for intense neutron source to develop fusion materials is described. (author)

17. IAEA fusion energy conference. Extended synopses

International Nuclear Information System (INIS)

1998-01-01

Book of extended synopses of the papers, accepted by a international programme committee for presentation at the 17th IAEA Fusion Energy Conference in Yokohama, Japan. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory

Fusion fuel blanket technology

International Nuclear Information System (INIS)

Hastings, I.J.; Gierszewski, P.

1987-05-01

The fusion blanket surrounds the burning hydrogen core of a fusion reactor. It is in this blanket that most of the energy released by the nuclear fusion of deuterium-tritium is converted into useful product, and where tritium fuel is produced to enable further operation of the reactor. As fusion research turns from present short-pulse physics experiments to long-burn engineering tests in the 1990's, energy removal and tritium production capabilities become important. This technology will involve new materials, conditions and processes with applications both to fusion and beyond. In this paper, we introduce features of proposed blanket designs and update and status of international research. In focusing on the Canadian blanket technology program, we discuss the aqueous lithium salt blanket concept, and the in-reactor tritium recovery test program

Fusion Reactor Materials

International Nuclear Information System (INIS)

Decreton, M.

2002-01-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

Japanese fusion research

International Nuclear Information System (INIS)

Uchida, T.

1987-01-01

The Japan experience during thirty years in nuclear fusion research is reported, after attending the 1st Geneva Conference in 1955, Osaka University, immedeately began linear pinch study using capacitor bank discharge. Subsequently to his trial several groups were organized to ward fusion R and D at universities in Tokyo, Nagoya, Kyoto, Sendai and son on. Based upon the recommendation of Japan Science Council, Institut of Plasma Physics (IPP) was established at Nagoya University in 1961 When the 1st International Conference on Plasma Physics and Controlled Nuclear Fusion Research was held in Saltzburg. The gloomy Bohm barrier had stood in front of many of experiments at that time. (author) [pt

International bulletin on atomic and molecular data for fusion. No. 54-55

International Nuclear Information System (INIS)

Stephens, J.A.

1998-12-01

This bulletin is published by the International Atomic Energy Agency to provide atomic and molecular data relevant to fusion research and technology. In the first part the indexed papers are listed separately for (i) structure and spectra (energy levels, wavelengths, transition probabilities, oscillator strengths, polarizabilities, electric moments, interatomic potentials), (ii) atomic and molecular collisions (photon collisions, electron collisions, heavy-particle collisions), and (iii) surface interactions (sputtering, chemical reactions, trapping and detrapping, adsorption, desorption, reflection, and secondary electron emission). There are also chapters with beam-matter interactions and data on interactions of atomic particles with fields. In the second Part contains the bibliographic data, essentially for the above listed topics

The Direct Internal Recycling concept to simplify the fuel cycle of a fusion power plant

International Nuclear Information System (INIS)

Day, Christian; Giegerich, Thomas

2013-01-01

Highlights: • The fusion fuel cycle is presented and its functions are discussed. • Tritium inventories are estimated for an early DEMO configuration. • The Direct Internal Recycling concept to reduce tritium inventories is described. • Concepts for its technical implementation are developed. -- Abstract: A new concept, the Direct Internal Recycling (DIR) concept, is proposed, which minimizes fuel cycle inventory by adding an additional short-cut between the pumped torus exhaust gas and the fuelling systems. The paper highlights quantitative modelling results derived from a simple fuel cycle spreadsheet which underline the potential benefits that can be achieved by implementation of the DIR concept into a fusion power plant. DIR requires a novel set-up of the torus exhaust pumping system, which replaces the batch-wise and cyclic operated cryogenic pumps by a continuous pumping solution and which offers at the same time an additional integral gas separation function. By that, hydrogen can be removed close to the divertor from all other gases and the main load to the fuel clean-up systems is a smaller, helium-rich gas stream. Candidate DIR relevant pump technology based on liquid metals (vapour diffusion and liquid ring pumps) and metal foils is discussed

Future directions in fusion research

International Nuclear Information System (INIS)

Clarke, J.F.

1987-01-01

The author discusses his analysis to quantify the priority of fusion R and D in the United States. The conclusion is that this priority has been essentially constant for 35 years with only two exceptions. He identifies four basic problems that must be solved. These problems are: to improve the scientific understanding of confinement concepts if we are going to have an energy source that can be utilized some day; to understand the physics of burning plasmas; to develop the materials for fusion use to realize the environmental potential of fusion; and to develop fusion nuclear technology. A response to these problems is given, based on the author's argument for international collaboration in fusion research

Description of card input data and formats for the International Bulletin on Atomic and Molecular Data for Fusion

International Nuclear Information System (INIS)

Katsonis, K.; Smith, F.J.

1979-05-01

This document describes the input data and the corresponding format of the computer programme which is used by the Atomic and Molecular Unit of the IAEA for storing, compiling and retrieving numerical data and/or bibliographic information for publishing the International Bulletin on Atomic and Molecular Data for Fusion

17. IAEA fusion energy conference. Extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

Book of extended synopses of the papers, accepted by a international programme committee for presentation at the 17th IAEA Fusion Energy Conference in Yokohama, Japan. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory Refs, figs, tabs

24. IAEA Fusion Energy Conference. Programme and Book of Abstracts

International Nuclear Information System (INIS)

2012-09-01

The International Atomic Energy Agency (IAEA) fosters the exchange of scientific and technical results in nuclear fusion research through its series of Fusion Energy Conferences. The 24th IAEA Fusion Energy Conference (FEC 2012) aims to provide a forum for the discussion of key physics and technology issues as well as innovative concepts of direct relevance to fusion as a source of nuclear energy. With a number of next-step fusion devices currently being implemented - such as the International Thermonuclear Experimental Reactor (ITER) in Cadarache, France, and the National Ignition Facility (NIF) in Livermore, USA - and in view of the concomitant need to demonstrate the technological feasibility of fusion power plants as well as the economical viability of this method of energy production, the fusion community is now facing new challenges. The resolution of these challenges will dictate research orientations in the present and coming decades. The scientific scope of FEC 2012 is, therefore, intended to reflect the priorities of this new era in fusion energy research. The conference aims to be a platform for sharing the results of research and development efforts in both national and international fusion experiments that have been shaped by these new priorities, and thereby help in pinpointing worldwide advances in fusion theory, experiments, technology, engineering, safety and socio-economics. Furthermore, the conference will also set these results against the backdrop of the requirements for a net energy producing fusion device and a fusion power plant in general, and will thus help in defining the way forward. With the participation of international organizations such as the ITER International Organization and EURATOM, as well as the collaboration of more than forty countries and several research institutes, including those working on smaller plasma devices, it is expected that this conference will, as in the past, serve to identify possibilities and means for a

Fusion energy 1998. Proceedings. V. 1-4

International Nuclear Information System (INIS)

1999-01-01

The 17-th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology

Fusion energy 1998. Proceedings. V. 1-4

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-01

The 17-th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology.

Compendium of structure and collision data in the first 12 issues of the international bulletin on atomic and molecular data for fusion

International Nuclear Information System (INIS)

Katsonis, K.; Rumble, J. Jr.

1980-06-01

This document is a compendium of the structure, spectra and collision data in the first 12 issues of the International Bulletin on Atomic and Molecular Data for Fusion. The Bulletin is issued quarterly by the International Atomic Energy Agency to assist the development of fusion research and technology. Not included in this compendium are those parts of the Bulletin concerned with Surface Effects, Work in Progress, Contributed Numerical Data, and Data Requests. Where necessary, corrections have been made to the data previously published to make the compendium as accurate as possible. The editors would appreciate any information on errors, duplications or omissions which would make future compendia more accurate and useful. (author)

International bulletin on atomic and molecular data for fusion. No. 16

International Nuclear Information System (INIS)

Katsonis, K.

1981-06-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. ''Data Request'' in the fusion field are also mentioned. The bulletin contains a list of references covering the years 1980 and 1981 for all the publications on controlled fusion and plasma physics

Status and development plan of nuclear fusion research in the US

International Nuclear Information System (INIS)

Kang Weihong

2012-01-01

This paper presents the background of nuclear fusion research and current status of major devices with accomplishments in the US, as well as the national fusion plans and budgets for fusion energy development by the US government. As a fusion power in the world, the US has made significant contributions to the development of international fusion research. The strategy of fusion research developments and the accomplishments may exert a subtle influence on international fusion development situation. Withdrawing from the ITER partnership for 2 times, the US rejoined it subsequently. This paper gives a brief introduction of changes in the US fusion research policy, summarizes the implementation of ITER procurement packages undertaken by the US, and the overview of the US inertial confinement fusion re- search. The US future energy development plan is the development of magnetic confinement fusion approach in parallel with inertial confinement fusion approach. (author)

FOREWORD: 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications/1st International Conference on Fusion Energy Materials Science 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications/1st International Conference on Fusion Energy Materials Science

Science.gov (United States)

Jacob, Wolfgang; Linsmeier, Christian; Rubel, Marek

2011-12-01

The 13th International Workshop on Plasma-Facing Materials and Components (PFMC-13) jointly organized with the 1st International Conference on Fusion Energy Materials Science (FEMaS-1) was held in Rosenheim (Germany) on 9-13 May 2011. PFMC-13 is a successor of the International Workshop on Carbon Materials for Fusion Applications series. Between 1985 and 2003 ten 'Carbon Workshops' were organized in Jülich, Stockholm and Hohenkammer. Then it was time for a change and redefinition of the scope of the symposium to reflect the new requirements of ITER and the ongoing evolution in the field. Under the new name (PFMC-11), the workshop was first organized in 2006 in Greifswald, Germany and PFMC-12 took place in Jülich in 2009. Initially starting in 1985 with about 40 participants as a 1.5 day workshop, the event has continuously grown to about 220 participants at PFMC-12. Due to the joint organization with FEMaS-1, PFMC-13 set a new record with more than 280 participants. The European project Fusion Energy Materials Science, FEMaS, coordinated by the Max-Planck-Institut für Plasmaphysik (IPP), organizes and stimulates cooperative research activities which involve large-scale research facilities as well as other top-level materials characterization laboratories. Five different fields are addressed: benchmarking experiments for radiation damage modelling, the application of micro-mechanical characterization methods, synchrotron and neutron radiation-based techniques and advanced nanoscopic analysis based on transmission electron microscopy. All these fields need to be exploited further by the fusion materials community for timely materials solutions for a DEMO reactor. In order to integrate these materials research fields, FEMaS acted as a co-organizer for the 2011 workshop and successfully introduced a number of participants from research labs and universities into the PFMC community. Plasma-facing materials experience particularly hostile conditions as they are

Fusion Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

Decreton, M

2002-04-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

Summary Report of the 1. Research Coordination Meeting on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF)

International Nuclear Information System (INIS)

Trkov, A.; Greenwood, L.R.; Simakov, S.P.

2013-09-01

In accordance with the recommendations of the International Nuclear Data Committee in May 2012, the Nuclear Data Section of IAEA has initiated a new Coordinated Research Project (CRP number F41031) with the main goal to test, validate and improve the international dosimetry library for fission and fusion (IRDFF). The output of this CRP will be a reference dosimetry database of cross sections and decay data with corresponding documentation. It will serve to the needs of fission, fusion and accelerator applications. The first Research Coordination Meeting (RCM) was held 1 to 5 July 2013 in IAEA. At this meeting, the attendees discussed the objectives of the whole CRP, presented their contributions and elaborated on consolidated recommendations and actions for implementation over the next 1.5 year period. This Summary Report documents the individual contributions and joint decisions made during this meeting. (author)

The dengue virus type 2 envelope protein fusion peptide is essential for membrane fusion

International Nuclear Information System (INIS)

Huang, Claire Y.-H.; Butrapet, Siritorn; Moss, Kelly J.; Childers, Thomas; Erb, Steven M.; Calvert, Amanda E.; Silengo, Shawn J.; Kinney, Richard M.; Blair, Carol D.; Roehrig, John T.

2010-01-01

The flaviviral envelope (E) protein directs virus-mediated membrane fusion. To investigate membrane fusion as a requirement for virus growth, we introduced 27 unique mutations into the fusion peptide of an infectious cDNA clone of dengue 2 virus and recovered seven stable mutant viruses. The fusion efficiency of the mutants was impaired, demonstrating for the first time the requirement for specific FP AAs in optimal fusion. Mutant viruses exhibited different growth kinetics and/or genetic stabilities in different cell types and adult mosquitoes. Virus particles could be recovered following RNA transfection of cells with four lethal mutants; however, recovered viruses could not re-infect cells. These viruses could enter cells, but internalized virus appeared to be retained in endosomal compartments of infected cells, thus suggesting a fusion blockade. Mutations of the FP also resulted in reduced virus reactivity with flavivirus group-reactive antibodies, confirming earlier reports using virus-like particles.

The ITER fusion reactor and its role in the development of a fusion power plant

International Nuclear Information System (INIS)

McLean, A.

2002-01-01

Energy from nuclear fusion is the future source of sustained, full life-cycle environmentally benign, intrinsically safe, base-load power production. The nuclear fusion process powers our sun, innumerable other stars in the sky, and some day, it will power the Earth, its cities and our homes. The International Thermonuclear Experimental Reactor, ITER, represents the next step toward fulfilling that promise. ITER will be a test bed for key steppingstones toward engineering feasibility of a demonstration fusion power plant (DEMO) in a single experimental step. It will establish the physics basis for steady state Tokamak magnetic containment fusion reactors to follow it, exploring ion temperature, plasma density and containment time regimes beyond the breakeven power condition, and culminating in experimental fusion self-ignition. (author)

19. IAEA fusion energy conference. Book of abstracts

International Nuclear Information System (INIS)

2002-01-01

Book of abstracts of the papers, accepted by an international programme committee for presentation at the 19th IAEA Fusion Energy Conference in Lyon, France. The subjects covered are magnetic confinement experiments, plasma heating and current drive, ITER EDA, inertial fusion energy, innovative concepts, fusion technology and theory

Evolution and results of LCT, international collaboration of superconducting coil development for fusion

International Nuclear Information System (INIS)

Shimamoto, Susumu

1987-01-01

This international collaboration has been promoted centering around the International Energy Agency since ten years ago. This work is that of advancing joint experiments on the equal footing by several countries gathering with large hardwares. As the result, unlike the international collaboration carried out so far, much experiences have been brought in. Now this work is going to be successfully completed. At this time, the realities of the international collaboration experienced through this work are reported while referring to a part of the technical results. Superconductors were found at the end of 1950s, and the technical development of superconducting coils has been advanced mainly for the equipment of high energy physics in foreign countries, while in Japan, for MHD electricity generation and magnetic levitation train. The TFTR (USA), JET (Euratom) and JT-60 (Japan) aiming at the attainment of critical plasma use normal conduction coils, but the agreement on the LCT project was signed in the autumn of 1977, which aims at the development of the superconducting coils for fusion experimental reactors. The development of coil manufacture in respective countries and the experiments in Japan and Euratom, some episode in the negotiation, the experiment on six coils and the results are reported. (Kako, I.)

What fusion means to Canada

International Nuclear Information System (INIS)

Bolton, R.A.

1983-06-01

Fusion can and will play an ever-increasing role in the energy balance once it has been brought on line. Taming of this technology and the maturing processes of engineering and economic feasibility will proceed at a rate which depends very strongly upon international and collective national wills to see it through. Large experimental devices, particularly of the tokamak type, are now being completed; their performance should give a very good idea of the scientific feasibility. The next-stage devices are at the pre-proposal and proposal stages but are not yet approved, even in principle. An improved general economic climate sustained for a few years would certainly help re-establish the momentum of world international efforts in fusion. This paper gives an overview of fusion research on a world scale and details of the particular aspects that Canada has chosen to pursue

Magnetic fusion energy. Part VI

International Nuclear Information System (INIS)

Anon.

1982-01-01

The first chapter of this part describes briefly the DOE policy for fusion energy. Subsequent chapters include: FY 1980 overview - activities of the Office of Fusion Energy; subactivity descriptions (confinement systems, development and technology, applied plasma physics, and reactor projects); field activities (DOE laboratories, educational institutions, nonprofit organizations, and commercial firms); commercialization; environmental implications; regional activities; and international programs

16. International Symposium on Heavy Ion Inertial Fusion (HIF'06)

International Nuclear Information System (INIS)

Adonin, A.; Ausset, P.; Babadunni, O.; Barnard, J.; Barriga-Carrasco, M.; Bawa, O.; Benedetti, C.; Bieniosek, F.; Bouchigny, S.; Bret, A.; Celata, Ch.; Chieze, J.P.; Coelho, L.F.; Cohen, R.; Coleman, J.; Cremer, S.; Crouseilles, N.; Davidson, R.; Debonnel, Ch.; Deutsch, C.; Didelez, J.P.; Efremov, V.; Fedosejevs, R.; Fertman, A.; Friedman, A.; Gardes, D.; Gericke, D.; Gilson, E.; Golubev, A.; Gombert, M.M.; Grisham, L.; Grote, D.; Gutnic, M.; Haber, I.; Hammel, B.; Hasegawa, J.; Hegelich, B.M.; Henestroza, E.; Hoffmann, D.H.H.; Horioka, K.; Jacoby, J.; Kaganovich, I.; Katagiri, K.; Kawata, S.; Kikuchi, T.; Kireeff Covo, M.; Kurilenkov, Y.; Latu, G.; Lenglet, A.; Logan, G.; Lund, St.; Maynard, G.; Molvik, A.; Nishinomiya, S.; Ogawa, M.; Oguri, Y.; Piriz, A.R.; Popoff, R.; Pusterla, M.; Qin, H.; Roth, M.; Roy, P.; Sant'Anna, M.; Sasaki, T.; Sefkow, A.; Seidl, P.; Sharkov, B.; Sharp, W.; Sonnendrucker, E.; Spiller, P.; Startsev, E.; Stoltz, P.; Synakowski, E.; Tahir, N.; Takayama, K.; Tashev, B.; Turchetti, G.; Turtikov, V.; Udrea, S.; Varentsov, D.; Vay, J.L.; Velarde, P.; Welch, D.R.; Westenskow, G.; Weyrich, K.; Yaramyshev, St.; Zenkevich, P.

2006-01-01

The contributions to this symposium have been divided into 8 issues: 1) overviews of national fusion programs, 2) other fusion programs, 3) accelerators, 4) warm dense matter, 5) ion beam neutralization, 6) atomic physics, 7) beam dynamics, and 8) stopping power. This document gathers only the resumes of the articles

16. International Symposium on Heavy Ion Inertial Fusion (HIF'06)

Energy Technology Data Exchange (ETDEWEB)

Adonin, A; Ausset, P; Babadunni, O; Barnard, J; Barriga-Carrasco, M; Bawa, O; Benedetti, C; Bieniosek, F; Bouchigny, S; Bret, A; Celata, Ch; Chieze, J P; Coelho, L F; Cohen, R; Coleman, J; Cremer, S; Crouseilles, N; Davidson, R; Debonnel, Ch; Deutsch, C; Didelez, J P; Efremov, V; Fedosejevs, R; Fertman, A; Friedman, A; Gardes, D; Gericke, D; Gilson, E; Golubev, A; Gombert, M M; Grisham, L; Grote, D; Gutnic, M; Haber, I; Hammel, B; Hasegawa, J; Hegelich, B M; Henestroza, E; Hoffmann, D H.H.; Horioka, K; Jacoby, J; Kaganovich, I; Katagiri, K; Kawata, S; Kikuchi, T; Kireeff Covo, M; Kurilenkov, Y; Latu, G; Lenglet, A; Logan, G; Lund, St; Maynard, G; Molvik, A; Nishinomiya, S; Ogawa, M; Oguri, Y; Piriz, A R; Popoff, R; Pusterla, M; Qin, H; Roth, M; Roy, P; Sant' Anna, M; Sasaki, T; Sefkow, A; Seidl, P; Sharkov, B; Sharp, W; Sonnendrucker, E; Spiller, P; Startsev, E; Stoltz, P; Synakowski, E; Tahir, N; Takayama, K; Tashev, B; Turchetti, G; Turtikov, V; Udrea, S; Varentsov, D; Vay, J L; Velarde, P; Welch, D R; Westenskow, G; Weyrich, K; Yaramyshev, St; Zenkevich, P

2006-07-01

The contributions to this symposium have been divided into 8 issues: 1) overviews of national fusion programs, 2) other fusion programs, 3) accelerators, 4) warm dense matter, 5) ion beam neutralization, 6) atomic physics, 7) beam dynamics, and 8) stopping power. This document gathers only the resumes of the articles.

On Korean strategy and plan for fusion energy

International Nuclear Information System (INIS)

Kim, H.J.; Choi, W-J.; Park, C.; Kim, H.C.

2012-01-01

In developing KSTAR (Korean Superconducting Tokamak Advanced Research), Korea had initiated a mid-entry strategy to catch up with the technologies required for the development of a fusion reactor, based on the tokamak magnetic confinement concept. Upon joining ITER (International Thermonuclear Experimental Reactor), Korean government enacted a promotional law for the fusion energy development. Under this promotional law the national promotional plans for developing fusion energy have been established. The National Fusion Research Institute (NFRI) developed the strategy and plan for a fusion DEMO program to realize the magnetic fusion energy. (author)

On Korean strategy and plan for fusion energy

Energy Technology Data Exchange (ETDEWEB)

Kim, H.J. [National Fusion Research Inst., Daejeon (Korea, Republic of); Choi, W-J. [Chungnam National Univ., Daejeon (Korea, Republic of); Park, C. [POSTECH, Pohang (Korea, Republic of); Kim, H.C. [National Fusion Research Inst., Daejeon (Korea, Republic of)

2012-07-01

In developing KSTAR (Korean Superconducting Tokamak Advanced Research), Korea had initiated a mid-entry strategy to catch up with the technologies required for the development of a fusion reactor, based on the tokamak magnetic confinement concept. Upon joining ITER (International Thermonuclear Experimental Reactor), Korean government enacted a promotional law for the fusion energy development. Under this promotional law the national promotional plans for developing fusion energy have been established. The National Fusion Research Institute (NFRI) developed the strategy and plan for a fusion DEMO program to realize the magnetic fusion energy. (author)

The growth of European fusion research

International Nuclear Information System (INIS)

Palumbo, D.

1988-01-01

The Euratom initial research programme with fusion as a modest element was constituted in 1958. Progress in fusion research mainly in the USA, USSR and UK was reported at the Geneva Conference held in September 1958. A network of national laboratories cooperating in fusion research was constituted under Association Contracts rather than founding a single Euratom laboratory. Emergence of the Tokamak became evident in 1968, and in 1969 a team from Culham travelled to Moscow to measure the electron plasma temperature and confirmed the previous Russian results. Collaboration between Culham and the European Fusion programme developed before the entrance of the UK into the European Community. The JET design team began its work in 1973. The site selected was at Culham and construction of JET commenced in 1978. Subsequent international discussions including the USA and USSR resulted in detailed design studies for a large device known as the INTOR Tokamak which will probably lead to further international cooperation. (U.K.)

Nuclear measurements, techniques and instrumentation, industrial applications, plasma physics and nuclear fusion 1986-1996. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1997-03-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Measurements, Techniques, and Instrumentation, Industrial Applications, Plasma Physics and Nuclear Fusion, issued during the period 1986-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. Contents cover the three main areas of (i) Nuclear Measurements, Techniques and Instrumentation (Physics, Dosimetry Techniques, Nuclear Analytical Techniques, Research Reactor and Particle Accelerator Applications, and Nuclear Data), (ii) Industrial Applications (Radiation Processing, Radiometry, and Tracers), and (iii) Plasma Physics and Controlled Thermonuclear Fusion

ITER implementation and fusion energy research in China

International Nuclear Information System (INIS)

Zhao, Jing; Feng, Zhaoliang; Yang, Changchun

2015-01-01

ITER Project is jointly implemented by China, EU, India, Japan, Korea, Russian Federation and USA, under the coordination of Center Team of ITER International Fusion Energy Organization (IO-CT). Chinese fusion research related institutes and industrial enterprises are fully involved in the implementation of China contribution to the project under the leadership of ITER China Domestic Agency (CN-DA), together with IO-CT. The progresses of Procurement Packages (PA) allocated to China and the technical issues, especially on key technology development and schedule, QA/QC issues, are highlighted in this report. The specific enterprises carrying out different PAs are identified in order to make the increasing international manufactures and producers to ITER PAs know each other well for the successful implementation of ITER project. The participation of China to the management of IO-CT is also included, mainly from the governmental aspect and staff recruited from China. On the other hand, the domestic fusion researches, including upgrade of EAST, HL-2A Tokamaks in China, TBM program, the next step design activities for fusion energy power plant, namely, CFETR and training in this area, are also introduced for global cooperation for international fusion community. (author)

The materials production and processing facility at the Spanish National Centre for fusion technologies (TechnoFusion)

International Nuclear Information System (INIS)

Munoz, A.; Monge, M.A.; Pareja, R.; Hernandez, M.T.; Jimenez-Rey, D.; Roman, R.; Gonzalez, M.; Garcia-Cortes, I.; Perlado, M.; Ibarra, A.

2011-01-01

In response to the urgent request from the EU Fusion Program, a new facility (TechnoFusion) for research and development of fusion materials has been planned with support from the Regional Government of Madrid and the Ministry of Science and Innovation of Spain. TechnoFusion, the National Centre for Fusion Technologies, aims screening different technologies relevant for ITER and DEMO environments while promoting the contribution of international companies and research groups into the Fusion Programme. For this purpose, the centre will be provided with a large number of unique facilities for the manufacture, testing (a triple-beam multi-ion irradiation, a plasma-wall interaction device, a remote handling for under ionizing radiation testing) and analysis of critical fusion materials. Particularly, the objectives, semi-industrial scale capabilities and present status of the TechnoFusion Materials Production and Processing (MPP) facility are presented. Previous studies revealed that the MPP facility will be a very promising infrastructure for the development of new materials and prototypes demanded by the fusion technology and therefore some of them will be here briefly summarized.

The materials production and processing facility at the Spanish National Centre for fusion technologies (TechnoFusion)

Energy Technology Data Exchange (ETDEWEB)

Munoz, A., E-mail: rpp@fis.uc3m.es [Departamento de Fisica, UC3M, Avda de la Universidad 30, 28911 Leganes, Madrid (Spain); Monge, M.A.; Pareja, R. [Departamento de Fisica, UC3M, Avda de la Universidad 30, 28911 Leganes, Madrid (Spain); Hernandez, M.T. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain); Jimenez-Rey, D. [CMAM, UAM, C/Faraday 3, 28049, Madrid (Spain); Roman, R.; Gonzalez, M.; Garcia-Cortes, I. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain); Perlado, M. [IFN, ETSII, UPM, C/Jose Gutierrez Abascal, 2, 28006 Madrid (Spain); Ibarra, A. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain)

2011-10-15

In response to the urgent request from the EU Fusion Program, a new facility (TechnoFusion) for research and development of fusion materials has been planned with support from the Regional Government of Madrid and the Ministry of Science and Innovation of Spain. TechnoFusion, the National Centre for Fusion Technologies, aims screening different technologies relevant for ITER and DEMO environments while promoting the contribution of international companies and research groups into the Fusion Programme. For this purpose, the centre will be provided with a large number of unique facilities for the manufacture, testing (a triple-beam multi-ion irradiation, a plasma-wall interaction device, a remote handling for under ionizing radiation testing) and analysis of critical fusion materials. Particularly, the objectives, semi-industrial scale capabilities and present status of the TechnoFusion Materials Production and Processing (MPP) facility are presented. Previous studies revealed that the MPP facility will be a very promising infrastructure for the development of new materials and prototypes demanded by the fusion technology and therefore some of them will be here briefly summarized.

Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2014

Energy Technology Data Exchange (ETDEWEB)

Wiffen, Frederick W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Noe, Susan P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Snead, Lance Lewis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2014-10-01

The realization of fusion energy is a formidable challenge with significant achievements resulting from close integration of the plasma physics and applied technology disciplines. Presently, the most significant technological challenge for the near-term experiments such as ITER, and next generation fusion power systems, is the inability of current materials and components to withstand the harsh fusion nuclear environment. The overarching goal of the ORNL fusion materials program is to provide the applied materials science support and understanding to underpin the ongoing DOE Office of Science fusion energy program while developing materials for fusion power systems. In doing so the program continues to be integrated both with the larger U.S. and international fusion materials communities, and with the international fusion design and technology communities.

Prospect of laser fusion power generation

International Nuclear Information System (INIS)

Nakai, Sadao

1998-01-01

Inertial fusion ignition, burn and energy gain are expected to be achieved within the first decade of next century with new Megajoule laser facilities which are under construction in the USA and France. Fusion reactor design studies indicate that Inertial Fusion Energy(IFE) power plants are technically feasible and have attractive safety and environmental features. The recent progress on implosion physics and relevant technologies require us to consider a strategic approach toward IFE development. The design study for a laser fusion power plant KOYO has been conducted as a joint program of universities, national laboratories and industries in Japan and also with international collaborations. The progress of high power laser technology gives us feasible project toward a laser driven IFE Power Plant. The technical breakthrough in the field of diode pumped solid state laser (DPSSL) has opened wide application of power laser to industrial technologies. Laser fusion energy development will be proceeded jointly with industrial photonics research and development. International collaborations are also promoted for efficient progress and activation of R and D on advanced technologies which are required for IFE and also useful for modern industries. (author). 7 refs., 1 tab., 7 figs

Thermonuclear fusion: Current status and future prospects

International Nuclear Information System (INIS)

Bruhns, H.; Maisonnier, Ch.

1992-01-01

Thermonuclear Fusion holds great promises for becoming an important energy source for the future. Fusion research and development is undertaken in al major countries of the world. The European Community pursues fusion in a large programme which embraces all R and D in the field of magnetic confinement fusion in the Member States, and to which Sweden and Switzerland are fully associated. The long-term objective of the programme is the joint creation of safe, environmentally sound prototype reactors. The main R and D line of the Community Fusion Programme is fusion by toroidal magnetic confinement on the basis of the Tokamak concept. Some related concepts are also studied which possibly could offer advantages for a reactor, and keep-in-touch activities exist for other approaches. Several small and medium sized specialised devices in Associated Laboratories have been built by the Community Fusion Programme as well as the Joint European Torus (JET Joint Undertaking) which is the largest and the most successful fusion device in the world. Recently, fusion power in the megawatt range has been achieved in JET. The long timescale and the large effort needed for the development of fusion as an energy source have been important elements to foster international collaboration. Engineering Design Activities for an International Thermonuclear Experimental Reactor (ITER) are undertaken, under the auspices of the IAEA, by the European Community, Japan, the Russian Federation and the United States of America. The objective of ITER is to achieve self-sustained thermonuclear burn and its control under long-pulse operation and to provide basic data for the engineering of a demonstration fusion reactor. (author)

Comparison of instrumented anterior interbody fusion with instrumented circumferential lumbar fusion.

Science.gov (United States)

Madan, S S; Boeree, N R

2003-12-01

Posterior lumbar interbody fusion (PLIF) restores disc height, the load bearing ability of anterior ligaments and muscles, root canal dimensions, and spinal balance. It immobilizes the painful degenerate spinal segment and decompresses the nerve roots. Anterior lumbar interbody fusion (ALIF) does the same, but could have complications of graft extrusion, compression and instability contributing to pseudarthrosis in the absence of instrumentation. The purpose of this study was to assess and compare the outcome of instrumented circumferential fusion through a posterior approach [PLIF and posterolateral fusion (PLF)] with instrumented ALIF using the Hartshill horseshoe cage, for comparable degrees of internal disc disruption and clinical disability. It was designed as a prospective study, comparing the outcome of two methods of instrumented interbody fusion for internal disc disruption. Between April 1994 and June 1998, the senior author (N.R.B.) performed 39 instrumented ALIF procedures and 35 instrumented circumferential fusion with PLIF procedures. The second author, an independent assessor (S.M.), performed the entire review. Preoperative radiographic assessment included plain radiographs, magnetic resonance imaging (MRI) and provocative discography in all the patients. The outcome in the two groups was compared in terms of radiological improvement and clinical improvement, measured on the basis of improvement of back pain and work capacity. Preoperatively, patients were asked to fill out a questionnaire giving their demographic details, maximum walking distance and current employment status in order to establish the comparability of the two groups. Patient assessment was with the Oswestry Disability Index, quality of life questionnaire (subjective), pain drawing, visual analogue scale, disability benefit, compensation status, and psychological profile. The results of the study showed a satisfactory outcome (scorelife questionnaire) score of 71.8% (28 patients) in

Fusion research program in Korea

International Nuclear Information System (INIS)

Hwang, Y.S.

1996-01-01

Fusion research in Korea is still premature, but it is a fast growing program. Groups in several universities and research institutes were working either in small experiments or in theoretical areas. Recently, couple of institutes who have small fusion-related experiments, proposed medium-size tokamak programs to jump into fusion research at the level of international recognition. Last year, Korean government finally approved to construct 'Superconducting Tokamak' as a national fusion program, and industries such as Korea Electric Power Corp. (KEPCO) and Samsung joined to support this program. Korea Basic Science Institute (KBSI) has organized national project teams including universities, research institutes and companies. National project teams are performing design works since this March. (author)

Overview of the European Fusion Programme

International Nuclear Information System (INIS)

Maisonnier, C.; Toschi, R.

1989-01-01

An overview of the European Fusion Programme is given and its near-term and long-term strategies are outlined. With the long-term energy problem worldwide as background, the role of thermonuclear fusion research is discussed in the context of energy sources having the potential to supply a substantial fraction of the electrical energy needs in the future. The European Fusion Programme, which is designed to lead in due course to the joint construction of prototypes with a view to their industrial production and marketing, is implemented by a sliding programme concept, i.e. through five-year programmes which overlap for about two years. The main objectives of the proposed 1987-1991 programme are outlined, with emphasis on the role of the Next Step (a Next European Torus or an International Thermonuclear Experimental Reactor), of the JET Joint Undertaking, of the Associated Laboratories, and of the European industry; and on the importance of international cooperation which has been established by bilateral framework agreements on fusion, by several multilateral implementing agreements in the frame of the IEA (OECD), and by the quadripartite cooperation of EURATOM, Japan, USA and USSR in the conceptual design of an International Thermonuclear Experimental Reactor under the auspices of the IAEA. (orig.)

EURATOM strategy towards fusion energy

International Nuclear Information System (INIS)

Varandas, C.

2007-01-01

Research and development (Research and Development) activities in controlled thermonuclear fusion have been carried out since the 60's of the last century aiming at providing a new clean, powerful, practically inexhaustive, safe, environmentally friend and economically attractive energy source for the sustainable development of our society.The EURATOM Fusion Programme (EFP) has the leadership of the magnetic confinement Research and Development activities due to the excellent results obtained on JET and other specialized devices, such as ASDEX-Upgrade, TORE SUPRA, FTU, TCV, TEXTOR, CASTOR, ISTTOK, MAST, TJ-II, W7-X, RFX and EXTRAP. JET is the largest tokamak in operation and the single device that can use deuterium and tritium mixes. It has produced 16 MW of fusion power, during 3 seconds, with an energy amplification of 0.6. The next steps of the EFP strategy towards fusion energy are ITER complemented by a vigorous Accompanying Programme, DEMO and a prototype of a fusion power plant. ITER, the first experimental fusion reactor, is a large-scale project (35-year duration, 10000 MEuros budget), developed in the frame of a very broad international collaboration, involving EURATOM, Japan, Russia Federation, United States of America, Korea, China and India. ITER has two main objectives: (i) to prove the scientific and technical viability of fusion energy by producing 500 MW, during 300 seconds and a energy amplification between 10 and 20; and (ii) to test the simultaneous and integrated operation of the technologies needed for a fusion reactor. The Accompanying Programme aims to prepare the ITER scientific exploitation and the DEMO design, including the development of the International Fusion Materials Irradiation Facility (IFMIF). A substantial part of this programme will be carried out in the frame of the Broader Approach, an agreement signed by EURATOM and Japan. The main goal of DEMO is to produce electricity, during a long time, from nuclear fusion reactions. The

Highlights of the heavy ion fusion symposium

International Nuclear Information System (INIS)

Keefe, D.

1986-01-01

The current status and prospects for inertial confinement fusion based on the use of intense beams of heavy ions will be described in the light of results presented at the International Symposium on Heavy Ion Fusion, (Washington, DC, May 27-29, 1986)

Highlights of the heavy ion fusion symposium

International Nuclear Information System (INIS)

Keefe, D.

1986-07-01

The current status and prospects for inertial confinement fusion based on the use of intense beams of heavy ions will be described in the light of results presented at the International Symposium on Heavy Ion Fusion, (Washington, DC, May 27-29, 1986)

FOREWORD: 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications

Science.gov (United States)

Kreter, Arkadi; Linke, Jochen; Rubel, Marek

2009-12-01

The 12th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-12) was held in Forschungszentrum Jülich (FZJ) in Germany in May 2009. This symposium is the successor to the International Workshop on Carbon Materials for Fusion Applications series. Between 1985 and 2003, 10 'Carbon Workshops' were organized in Jülich, Stockholm and Hohenkammer. After this time, the scope of the symposium was redefined to reflect the new requirements of ITER and the ongoing evolution of the field. The workshop was first organized under its new name in 2006 in Greifswald, Germany. The main objective of this conference series is to provide a discussion forum for experts from research institutions and industry dealing with materials for plasma-facing components in present and future controlled fusion devices. The operation of ASDEX-Upgrade with tungsten-coated wall, the fast progress of the ITER-Like Wall Project at JET, the plans for the EAST tokamak to install tungsten, the start of ITER construction and a discussion about the wall material for DEMO all emphasize the importance of plasma-wall interactions and component behaviour, and give much momentum to the field. In this context, the properties and behaviour of beryllium, carbon and tungsten under plasma impact are research topics of foremost relevance and importance. Our community realizes both the enormous advantages and serious drawbacks of all the candidate materials. As a result, discussion is in progress as to whether to use carbon in ITER during the initial phase of operation or to abandon this element and use only metal components from the start. There is broad knowledge about carbon, both in terms of its excellent power-handling capabilities and the drawbacks related to chemical reactivity with fuel species and, as a consequence, about problems arising from fuel inventory and dust formation. We are learning continuously about beryllium and tungsten under fusion conditions, but our

Agreement on the establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project. Latest status. Declarations/reservations

International Nuclear Information System (INIS)

2007-01-01

The Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project, for which the Director General of the IAEA is depositary, was done in Paris on 21 November 2006. Pursuant to Article 22 thereof, the Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project 'shall enter into force thirty days after the deposit of instruments of ratification, acceptance or approval of this Agreement by the People's Republic of China, EURATOM, the Republic of India, Japan, the Republic of Korea, the Russian Federation and the United States of America. The text of the Agreement is reproduced in the Annex hereto for the information of all Member States

Fusion energy research for ITER and beyond

International Nuclear Information System (INIS)

Romanelli, Francesco; Laxaaback, Martin

2011-01-01

The achievement in the last two decades of controlled fusion in the laboratory environment is opening the way to the realization of fusion as a source of sustainable, safe and environmentally responsible energy. The next step towards this goal is the construction of the International Thermonuclear Experimental Reactor (ITER), which aims to demonstrate net fusion energy production on the reactor scale. This paper reviews the current status of magnetic confinement fusion research in view of the ITER project and provides an overview of the main remaining challenges on the way towards the realization of commercial fusion energy production in the second half of this century. (orig.)

International bulletin on atomic and molecular data for fusion. No. 14

International Nuclear Information System (INIS)

Katsonis, K.

1980-11-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. The bulletin contains a list of references covering the year 1980 for all the publications on controlled fusion and plasma physics

International bulletin on atomic and molecular data for fusion. No. 20

International Nuclear Information System (INIS)

Katsonis, K.

1982-09-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. The bulletin contains a list of references covering the year 1982 for all the publications on controlled thermonuclear fusion and plasma physics

Academic Training: New Trends in Fusion Research

CERN Multimedia

Françoise Benz

2004-01-01

11, 12 and 13 October 2004-2005 ACADEMIC TRAINING PROGRAMME LECTURE SERIES 11 October from 11.00 to 12.00 hrs, 12 and 13 October from 10.00 to 12.00 hrs - 11 and 12 October in the Main Auditorium, bldg. 500, 13 October in the TH Amphitheatre New Trends in Fusion Research A. FASOLI / EPFL, Lausanne, CH The efforts of the international fusion community aim at demonstrating the scientific feasibility of thermonuclear fusion energy power plants. Understanding the behavior of burning plasmas, i.e. plasmas with strong self-heating, represents a primary scientific challenge for fusion research and a new science frontier. Although integrated studies will only be possible, in new, dedicated experimental facilities, such as the International Tokamak Experimental Reactor (ITER), present devices can address specific issues in regimes relevant to burning plasmas. Among these are an improvement of plasma performance via a reduction of the energy and particle transport, an optimization of the path to ignition or to su...

Academic Training: New Trends in Fusion Research

CERN Multimedia

Françoise Benz

2004-01-01

11, 12 and 13 October 2004-2005 ACADEMIC TRAINING PROGRAMME LECTURE SERIES 11 October from 11.00 to 12.00 hrs, 12 and 13 October from 10.00 to 12.00 hrs - 11 and 12 October in the Main Auditorium, bldg. 500, 13 October in the Theory Conference Room, bldg. 4 New Trends in Fusion Research A. FASOLI / EPFL, Lausanne, CH The efforts of the international fusion community aim at demonstrating the scientific feasibility of thermonuclear fusion energy power plants. Understanding the behavior of burning plasmas, i.e. plasmas with strong self-heating, represents a primary scientific challenge for fusion research and a new science frontier. Although integrated studies will only be possible, in new, dedicated experimental facilities, such as the International Tokamak Experimental Reactor (ITER), present devices can address specific issues in regimes relevant to burning plasmas. Among these are an improvement of plasma performance via a reduction of the energy and particle transport, an optimization of the path to i...

Fusion the energy of the universe

CERN Document Server

McCracken, Garry

2012-01-01

Fusion: The Energy of the Universe, 2e is an essential reference providing basic principles of fusion energy from its history to the issues and realities progressing from the present day energy crisis. The book provides detailed developments and applications for researchers entering the field of fusion energy research. This second edition includes the latest results from the National Ignition Facility at the Lawrence Radiation Laboratory at Livermore, CA, and the progress on the International Thermonuclear Experimental Reactor (ITER) tokamak programme at Caderache, France.

Fusion Technology for ITER, the ITER Project. Further Development Towards a DEMO Fusion Power Plant (3/4)

CERN Multimedia

CERN. Geneva

2011-01-01

This is the second half of a lecture series on fusion and will concentrate on fusion technology. The early phase of fusion development was concentrated on physics. However, during the 1980s it was realized that if one wanted to enter the area of fusion reactor plasmas, even in an experimental machine, a significant advance in fusion technologies would be needed. After several conceptual studies of reactor class fusion devices in the 1980s the engineering design phase of ITER started in earnest during the 1990s. The design team was in the beginning confronted with many challenges in the fusion technology area as well as in physics for which no readily available solution existed and in a few cases it was thought that solutions may be impossible to find. However, after the initial 3 years of intensive design and R&D work in an international framework utilizing basic fusion technology R&D from the previous decade it became clear that for all problems a conceptual solution could be found and further devel...

Nuclear Fusion Fuel Cycle Research Perspectives

International Nuclear Information System (INIS)

Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin; Yun, Sei-Hun

2015-01-01

As a part of the International Thermonuclear Experimental Reactor (ITER) Project, we at the Korea Atomic Energy Research Institute (KAERI) and our National Fusion Research Institute (NFRI) colleagues are investigating nuclear fusion fuel cycle hardware including a nuclear fusion fuel Storage and Delivery System (SDS). To have a better knowledge of the nuclear fusion fuel cycle, we present our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). To have better knowledge of the nuclear fusion fuel cycle, we presented our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). Our efforts to enhance the tritium confinement will be continued for the development of cleaner nuclear fusion power plants

Canadian fusion program

International Nuclear Information System (INIS)

Brown, T.S.

1982-06-01

The National Research Council of Canada is establishing a coordinated national program of fusion research and development that is planned to grow to a total annual operating level of about $20 million in 1985. The long-term objective of the program is to put Canadian industry in a position to manufacture sub-systems and components of fusion power reactors. In the near term the program is designed to establish a minimum base of scientific and technical expertise sufficient to make recognized contributions and thereby gain access to the international effort. The Canadian program must be narrowly focussed on a few specializations where Canada has special indigenous skills or technologies. The programs being funded are the Tokamak de Varennes, the Fusion Fuels Technology Project centered on tritium management, and high-power gas laser technology and associated diagnostic instrumentation

16. International Symposium on Heavy Ion Inertial Fusion (HIF'06)

Energy Technology Data Exchange (ETDEWEB)

Adonin, A.; Ausset, P.; Babadunni, O.; Barnard, J.; Barriga-Carrasco, M.; Bawa, O.; Benedetti, C.; Bieniosek, F.; Bouchigny, S.; Bret, A.; Celata, Ch.; Chieze, J.P.; Coelho, L.F.; Cohen, R.; Coleman, J.; Cremer, S.; Crouseilles, N.; Davidson, R.; Debonnel, Ch.; Deutsch, C.; Didelez, J.P.; Efremov, V.; Fedosejevs, R.; Fertman, A.; Friedman, A.; Gardes, D.; Gericke, D.; Gilson, E.; Golubev, A.; Gombert, M.M.; Grisham, L.; Grote, D.; Gutnic, M.; Haber, I.; Hammel, B.; Hasegawa, J.; Hegelich, B.M.; Henestroza, E.; Hoffmann, D.H.H.; Horioka, K.; Jacoby, J.; Kaganovich, I.; Katagiri, K.; Kawata, S.; Kikuchi, T.; Kireeff Covo, M.; Kurilenkov, Y.; Latu, G.; Lenglet, A.; Logan, G.; Lund, St.; Maynard, G.; Molvik, A.; Nishinomiya, S.; Ogawa, M.; Oguri, Y.; Piriz, A.R.; Popoff, R.; Pusterla, M.; Qin, H.; Roth, M.; Roy, P.; Sant' Anna, M.; Sasaki, T.; Sefkow, A.; Seidl, P.; Sharkov, B.; Sharp, W.; Sonnendrucker, E.; Spiller, P.; Startsev, E.; Stoltz, P.; Synakowski, E.; Tahir, N.; Takayama, K.; Tashev, B.; Turchetti, G.; Turtikov, V.; Udrea, S.; Varentsov, D.; Vay, J.L.; Velarde, P.; Welch, D.R.; Westenskow, G.; Weyrich, K.; Yaramyshev, St.; Zenkevich, P

2006-07-01

The contributions to this symposium have been divided into 8 issues: 1) overviews of national fusion programs, 2) other fusion programs, 3) accelerators, 4) warm dense matter, 5) ion beam neutralization, 6) atomic physics, 7) beam dynamics, and 8) stopping power. This document gathers only the resumes of the articles.

Helical-type device and laser fusion. Rivals for tokamak-type device at n-fusion development in Japan

International Nuclear Information System (INIS)

Anon.

1994-01-01

Under the current policy on the research and development of nuclear fusion in Japan, as enunciated by the Atomic Energy Commission of Japan, the type of a prototype fusion reactor will be chosen after 2020 from tokamak, helical or some other type including the inertial confinement fusion using lasers. A prototype fusion reactor is the next step following the tokamak type International Thermonuclear Experimental Reactor (ITER). With the prototype reactor, the feasibility as a power plant will be examined. At present the main research and development of nuclear fusion in Japan are on tokamak type, which have been promoted by Japan Atomic Energy Research Institute (JAERI). As for the other types of nuclear fusion, researches have been carried out on the helical type in Kyoto University and National Institute for Fusion Science (NIFS), the mirror type in Tsukuba University, the tokamak type using superconductive coils in Kyushu University, and the laser fusion in Osaka University. The features and the present state of research and development of the Large Helical Device and the laser fusion which is one step away from the break-even condition are reported. (K.I.)

Planning for U.S. Fusion Community Participation in the ITER Program

International Nuclear Information System (INIS)

Baker, Charles; Berk, Herbert; Greenwald, Martin; Mauel, Michael E.; Najmabadi, Farrokh; Nevins, William M.; Stambaugh, Ronald; Synakowski, Edmund; Batchelor, Donald B.; Fonck, Raymond; Hawryluk, Richard J.; Meade, Dale M.; Neilson, George H.; Parker, Ronald; Strait, Ted

2006-01-01

A central step in the mission of the U.S. Fusion Energy Sciences program is the creation and study of a fusion-powered 'star on earth', where the same energy source that drives the sun and other stars is reproduced and controlled for sustained periods in the laboratory. This ''star'' is formed by an ionized gas, or plasma, heated to fusion temperatures in a magnetic confinement device known as a tokamak, which is the most advanced magnetic fusion concept. The ITER tokamak is designed to be the premier scientific tool for exploring and testing expectations for plasma behavior in the fusion burning plasma regime, wherein the fusion process itself provides the dominant heat source to sustain the plasma temperature. It will provide the scientific basis and control tools needed to move toward the fusion energy goal. The ITER project confronts the grand challenge of creating and understanding a burning plasma for the first time. The distinguishing characteristic of a burning plasma is the tight coupling between the fusion heating, the resulting energetic particles, and the confinement and stability properties of the plasma. Achieving this strongly coupled burning state requires resolving complex physics issues and integrating challenging technologies. A clear and comprehensive scientific understanding of the burning plasma state is needed to confidently extrapolate plasma behavior and related technology beyond ITER to a fusion power plant. Developing this predictive understanding is the overarching goal of the U.S. Fusion Energy Sciences program. The burning plasma research program in the U.S. is being organized to maximize the scientific benefits of U.S. participation in the international ITER experiment. It is expected that much of the research pursued on ITER will be based on the scientific merit of proposed activities, and it will be necessary to maintain strong fusion research capabilities in the U.S. to successfully contribute to the

Planning for U.S. Fusion Community Participation in the ITER Program

Energy Technology Data Exchange (ETDEWEB)

Baker, Charles [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Berk, Herbert [Univ. of Texas, Austin, TX (United States); Greenwald, Martin [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Mauel, Michael E. [Columbia Univ., New York, NY (United States); Najmabadi, Farrokh [Univ. of California, San Diego, CA (United States); Nevins, William M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Stambaugh, Ronald [General Atomics, La Jolla, CA (United States); Synakowski, Edmund [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Batchelor, Donald B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Fonck, Raymond [Univ. of Wisconsin, Madison, WI (United States); Hawryluk, Richard J. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Meade, Dale M. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Neilson, George H. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Parker, Ronald [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Strait, Ted [General Atomics, La Jolla, CA (United States)

2006-06-07

A central step in the mission of the U.S. Fusion Energy Sciences program is the creation and study of a fusion-powered "star on earth", where the same energy source that drives the sun and other stars is reproduced and controlled for sustained periods in the laboratory. This “star” is formed by an ionized gas, or plasma, heated to fusion temperatures in a magnetic confinement device known as a tokamak, which is the most advanced magnetic fusion concept. The ITER tokamak is designed to be the premier scientific tool for exploring and testing expectations for plasma behavior in the fusion burning plasma regime, wherein the fusion process itself provides the dominant heat source to sustain the plasma temperature. It will provide the scientific basis and control tools needed to move toward the fusion energy goal. The ITER project confronts the grand challenge of creating and understanding a burning plasma for the first time. The distinguishing characteristic of a burning plasma is the tight coupling between the fusion heating, the resulting energetic particles, and the confinement and stability properties of the plasma. Achieving this strongly coupled burning state requires resolving complex physics issues and integrating challenging technologies. A clear and comprehensive scientific understanding of the burning plasma state is needed to confidently extrapolate plasma behavior and related technology beyond ITER to a fusion power plant. Developing this predictive understanding is the overarching goal of the U.S. Fusion Energy Sciences program. The burning plasma research program in the U.S. is being organized to maximize the scientific benefits of U.S. participation in the international ITER experiment. It is expected that much of the research pursued on ITER will be based on the scientific merit of proposed activities, and it will be necessary to maintain strong fusion research capabilities in the U.S. to successfully contribute to the success of ITER and optimize

International bulletin on atomic and molecular data for fusion. No. 9

International Nuclear Information System (INIS)

Katsonis, K.; Rumble, J. Jr.; Smith, F.J.

1979-07-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains a list of references covering the years 1978 and 1979 for all the publications on controlled fusion and plasma physics

International bulletin on atomic and molecular data for fusion. No. 15

International Nuclear Information System (INIS)

Katsonis, K.

1981-03-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains a list of references covering the years 1980 and 1981 for all the publications on controlled fusion and plasma physics

International bulletin on atomic and molecular data for fusion. No. 7

International Nuclear Information System (INIS)

Katsonis, K.; Smith, F.J.

1979-01-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains an extensive list of references covering the years 1977 and 1978 for all the publications on control fusion and plasma physics

International bulletin on atomic and molecular data for fusion. No. 19

International Nuclear Information System (INIS)

Katsonis, K.

1982-06-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains a list of references covering the years 1981 and 1982 for all the publications on controlled fusion and plasma physics

Utilization of a Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research. Report of a Coordinated Research Project 2011–2016

International Nuclear Information System (INIS)

2016-12-01

The IAEA actively promotes the development of controlled fusion as a source of energy. Through its coordinated research activities, the IAEA helps Member States to exchange and establish scientific and technical knowledge required for the design, construction and operation of a fusion reactor. Due to their compactness, flexibility and low operation costs, small fusion devices are a great resource for supporting and accelerating the development of mainstream fusion research on large fusion devices such as the International Thermonuclear Experimental Reactor. They play an important role in investigating the physics of controlled fusion, developing innovative technologies and diagnostics, testing new materials, training highly qualified personnel for larger fusion facilities, and supporting educational programmes for young scientists. This publication reports on the research work accomplished within the framework of the Coordinated Research Project (CRP) on Utilization of the Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research, organized and conducted by the IAEA in 2011–2016. The CRP has contributed to the coordination of a network of research institutions, thereby enhancing international collaboration through scientific visits, joint experiments and the exchange of information and equipment. A total of 16 institutions and 14 devices from 13 Member States participated in this CRP (Belgium, Bulgaria, Canada, China, Costa Rica, the Czech Republic, the Islamic Republic of Iran, Kazakhstan, Pakistan, Portugal, the Russian Federation, Ukraine and the United Kingdom).

Safety considerations in next step fusion design and beyond

International Nuclear Information System (INIS)

Holland, D.F.

1990-01-01

Recent U.S. and international design studies provide insights into the potential safety and environmental advantages of fusion as well as the development needed to realize this potential. We in the Fusion Safety Program at EG ampersand G Idaho have analyzed the Compact Ignition Tokamak (CIT), the International Thermonuclear Engineering Reactor (ITER), and the Advanced Reactor Innovative Engineering Study (ARIES). I have reviewed these three designs to determine issues related to meeting the safety and the environmental goals that guide fusion development in the U.S. The paper lists safety and environmental issues that are generic to fusion and approaches to favorably resolve each issue. The technical developments that have the highest potential of contributing to improving the safety and environmental attractiveness of fusion are identified and discussed. These developments are in the areas of low-activation materials, plasma- facing components, and plasma physics relating to off-normal plasma events and tritium burn-up. 8 refs., 7 tabs

Nuclear Fusion prize laudation Nuclear Fusion prize laudation

Science.gov (United States)

Burkart, W.

2011-01-01

Clean energy in abundance will be of critical importance to the pursuit of world peace and development. As part of the IAEA's activities to facilitate the dissemination of fusion related science and technology, the journal Nuclear Fusion is intended to contribute to the realization of such energy from fusion. In 2010, we celebrated the 50th anniversary of the IAEA journal. The excellence of research published in the journal is attested to by its high citation index. The IAEA recognizes excellence by means of an annual prize awarded to the authors of papers judged to have made the greatest impact. On the occasion of the 2010 IAEA Fusion Energy Conference in Daejeon, Republic of Korea at the welcome dinner hosted by the city of Daejeon, we celebrated the achievements of the 2009 and 2010 Nuclear Fusion prize winners. Steve Sabbagh, from the Department of Applied Physics and Applied Mathematics, Columbia University, New York is the winner of the 2009 award for his paper: 'Resistive wall stabilized operation in rotating high beta NSTX plasmas' [1]. This is a landmark paper which reports record parameters of beta in a large spherical torus plasma and presents a thorough investigation of the physics of resistive wall mode (RWM) instability. The paper makes a significant contribution to the critical topic of RWM stabilization. John Rice, from the Plasma Science and Fusion Center, MIT, Cambridge is the winner of the 2010 award for his paper: 'Inter-machine comparison of intrinsic toroidal rotation in tokamaks' [2]. The 2010 award is for a seminal paper that analyzes results across a range of machines in order to develop a universal scaling that can be used to predict intrinsic rotation. This paper has already triggered a wealth of experimental and theoretical work. I congratulate both authors and their colleagues on these exceptional papers. W. Burkart Deputy Director General Department of Nuclear Sciences and Applications International Atomic Energy Agency, Vienna

Antibody-Induced Internalization of the Human Respiratory Syncytial Virus Fusion Protein.

Science.gov (United States)

Leemans, A; De Schryver, M; Van der Gucht, W; Heykers, A; Pintelon, I; Hotard, A L; Moore, M L; Melero, J A; McLellan, J S; Graham, B S; Broadbent, L; Power, U F; Caljon, G; Cos, P; Maes, L; Delputte, P

2017-07-15

Respiratory syncytial virus (RSV) infections remain a major cause of respiratory disease and hospitalizations among infants. Infection recurs frequently and establishes a weak and short-lived immunity. To date, RSV immunoprophylaxis and vaccine research is mainly focused on the RSV fusion (F) protein, but a vaccine remains elusive. The RSV F protein is a highly conserved surface glycoprotein and is the main target of neutralizing antibodies induced by natural infection. Here, we analyzed an internalization process of antigen-antibody complexes after binding of RSV-specific antibodies to RSV antigens expressed on the surface of infected cells. The RSV F protein and attachment (G) protein were found to be internalized in both infected and transfected cells after the addition of either RSV-specific polyclonal antibodies (PAbs) or RSV glycoprotein-specific monoclonal antibodies (MAbs), as determined by indirect immunofluorescence staining and flow-cytometric analysis. Internalization experiments with different cell lines, well-differentiated primary bronchial epithelial cells (WD-PBECs), and RSV isolates suggest that antibody internalization can be considered a general feature of RSV. More specifically for RSV F, the mechanism of internalization was shown to be clathrin dependent. All RSV F-targeted MAbs tested, regardless of their epitopes, induced internalization of RSV F. No differences could be observed between the different MAbs, indicating that RSV F internalization was epitope independent. Since this process can be either antiviral, by affecting virus assembly and production, or beneficial for the virus, by limiting the efficacy of antibodies and effector mechanism, further research is required to determine the extent to which this occurs in vivo and how this might impact RSV replication. IMPORTANCE Current research into the development of new immunoprophylaxis and vaccines is mainly focused on the RSV F protein since, among others, RSV F-specific antibodies are

Proceedings of the third IEA international workshop on beryllium technology for fusion

International Nuclear Information System (INIS)

Kawamura, Hiroshi; Okamoto, Makoto

1998-01-01

This report is the Proceedings of the Third International Energy Agency International Workshop on Beryllium Technology for Fusion. The workshop was held on October 22-24, 1997, at the Sangyou Kaikan in Mito City with 68 participants who attended from the Europe, the Russian Federation, the Kazakstan, the United States and Japan. The topics for papers were arranged into 9 sessions; beryllium applications for ITER, production and characterization, chemical compatibility and corrosion, forming and joining, plasma/tritium interactions, beryllium coating, first wall applications, neutron irradiation effects, health and safety. To utilize beryllium in the pebble type blanket, a series of discussions were intensified in multiple view points such as the swelling, He/T release from beryllium pebble irradiated up to high He content, effective thermal conductivity, tritium permeation and coating, and fabrication cost, and so on. As the plasma facing material, life time of beryllium and coated beryllium, dust and particle production, joining, waste treatment, mechanical properties and deformation by swelling were discussed as important issues. Especially, it was recognized throughout the discussions that the comparative study by the different researchers should be carried out to establish the reliability of the data reported in the workshop and in others. To enhance the comparative study, the world wide collaboration for the relative evaluation of the beryllium was proposed by the International Organization Committee and the proposal was approved by all of the participants. The 45 of the presented papers are indexed individually. (J.P.N.)

International bulletin on atomic and molecular data for fusion. No. 22

International Nuclear Information System (INIS)

Katsonis, K.

1983-05-01

This bulletin deals with atomic and molecular data for fusion. Work in progress is briefly reported (charge exchange of slow ionized ions with neutral gases, cross section for electron impact ionization of Alt). The bulletin contains a list of references covering the years 1981, 1982 and 1983 for publications on controlled thermonuclear fusion and plasma physics

International bulletin on atomic and molecular data for fusion. No. 8

International Nuclear Information System (INIS)

Katsonis, K.; Smith, F.J.

1979-04-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported. The bulletin contains an extensive list of references covering the year 1978 and the beginning of 1979 for all the publications on control fusion and plasma physics

Joint Varenna-Lausanne International Workshop on the Theory of Fusion Plasmas 2016

International Nuclear Information System (INIS)

2016-01-01

The joint Varenna-Lausanne international workshop on the theory of fusion plasmas took place in Varenna from August 29 to September 2 2016. Several issues of interest for fusion plasmas were addressed, namely MHD stability, RF heating, collisional and turbulent transport, plasma wall interaction, and physics of burning plasmas. The articles published in this special issue illustrate nicely the well balanced combination of physics, applied mathematics, and computer sciences that characterizes this workshop. Let us mention several attractive topics, which are addressed in this issue. The question of 3D MHD equilibrium in tokamaks has received a great deal of attention, in connection with external resonant magnetic perturbations in tokamaks, and also stochastic edge in stellarators. The reader will also find some recent developments related to the effect of current drive and heating on the stability of tearing modes. As usual, turbulent transport is addressed in much detail. Several papers address specific numerical aspects of fluid and gyrokinetic codes, including code optimisation. Physics issues are abundantly dealt with, such as the impact of fast particles on turbulence, and particle transport. New numerical techniques to model wave propagation are presented, which provide significant advances in the field. Refinements such as the effect of density fluctuation on wave propagation, or the interaction between particles and the electromagnetic field near antennas, have also been studied in depth. Finally, specific issues such as nonlocal transport, decay of zonal flows, and the effect of neutrals on rotation have been investigated. A striking feature of the 2016 edition was the large number of young faces among the participants. This is a great satisfaction for the organizers since a new generation of scientists is certainly needed whilst several devices come to operation, or will do so in a foreseeable future. The diversity and quality of the papers published in

Fusion research at Culham site

International Nuclear Information System (INIS)

Tolonen, P.; Toppila, T.

1998-01-01

One of the many targets on the Finnish Nuclear Society (ATS) excursion to England was the Culham fusion research site. The site has divided into two parts. One of them is UKAEA Fusion with small scale fusion reactors and 200 employees. UKAEA has 3 fusion reactors at Culham site. One of is the START (Small Tight Aspect Ratio Tokamak) which was operational since 1991 but is today already out of operation. UKAEA has been operating a JET-like tokamak fusion reactor COMPASS-D since 1989. The latest of three reactors is MAST (Mega Amp Spherical Tokamak), which is still under construction. The first plasma will take place in the end of 1998. Another part of Culham site is JET (Joint European Torus), an all-European fusion undertaking with 350 employees. 150 of them are from various European countries and the rest 200 are employed by UKAEA. JET is the biggest fusion reactor ever and it represents the latest step in world wide fusion programme. In October 1997 JET achieved a world record in fusion power and energy. JET produced 16,1 MW power for 1 s and totally 21,7 MJ energy. This is the closest attempt to achieve break-even conditions. The next step in world wide fusion programme will be international ITER-reactor. This undertaking has some financial problems, since United States has taken distance to magnetic fusion research and moved closer to inertial fusion with funding of US Department of Defence. The planned reactor, however, is physically twice as big as JET. The step after this phase will be DEMO, which is purposed to produce fusion energy. According to our hosts in Culham this phase is 40 years ahead. (author)

Fusion Policy Advisory Committee (FPAC)

International Nuclear Information System (INIS)

1990-09-01

This document is the final report of the Fusion Policy Advisory Committee. The report conveys the Committee's views on the matters specified by the Secretary in his charge and subsequent letters to the Committee, and also satisfies the provisions of Section 7 of the Magnetic Fusion Energy Engineering Act of 1980, Public Law 96-386, which require a triennial review of the conduct of the national Magnetic Fusion Energy program. Three sub-Committee's were established to address the large number of topics associated with fusion research and development. One considered magnetic fusion energy, a second considered inertial fusion energy, and the third considered issues common to both. For many reasons, the promise of nuclear fusion as a safe, environmentally benign, and affordable source of energy is bright. At the present state of knowledge, however, it is uncertain that this promise will become reality. Only a vigorous, well planned and well executed program of research and development will yield the needed information. The Committee recommends that the US commit to a plan that will resolve this critically important issue. It also outlines the first steps in a development process that will lead to a fusion Demonstration Power Plant by 2025. The recommended program is aggressive, but we believe the goal is reasonable and attainable. International collaboration at a significant level is an important element in the plan

Simulation for evaluation of the multi-ion-irradiation Laboratory of TechnoFusion facility and its relevance for fusion applications

International Nuclear Information System (INIS)

Jimenez-Rey, D.; Mota, F.; Vila, R.; Ibarra, A.; Ortiz, Christophe J.; Martinez-Albertos, J.L.; Roman, R.; Gonzalez, M.; Garcia-Cortes, I.; Perlado, J.M.

2011-01-01

Thermonuclear fusion requires the development of several research facilities, in addition to ITER, needed to advance the technologies for future fusion reactors. TechnoFusion will focus in some of the priority areas identified by international fusion programmes. Specifically, the TechnoFusion Area of Irradiation of Materials aims at surrogating experimentally the effects of neutron irradiation on materials using a combination of ion beams. This paper justifies this approach using computer simulations to validate the multi-ion-irradiation Laboratory. The planned irradiation facility will investigate the effects of high energetic radiations on reactor-relevant materials. In a second stage, it will also be used to analyze the performance of such materials and evaluate newly designed materials. The multi-ion-irradiation Laboratory, both triple irradiation and high-energy proton irradiation, can provide valid experimental techniques to reproduce the effect of neutron damage in fusion environment.

Fusion energy and Canada's role

International Nuclear Information System (INIS)

Drolet, T.S.

1992-01-01

Fusion is the process of releasing energy from matter which occurs in our sun. Canada is contributing to the development of technology which will permit this process to be harnessed and made available on earth. The international effort has increased from a modest beginning in the 1950s to a level of approximately two billion dollars annually in the 1980s. The purpose of this booklet is to introduce the concept of fusion energy as a technology which should make an important addition to the mix of energy sources for our future. Through a co-ordinated approach, Canada has established several projects which will contribute significantly to the development of technologies in specific areas leading to opportunities now for Canadian industry in the international effort

The development of controlled nuclear fusion

International Nuclear Information System (INIS)

Pease, R.S.

1978-01-01

The high temperature conditions needed in a controlled nuclear fusion reactor are now being approached in experiments using magnetic fields to confine and isolate the plasma, especially in systems of the tokamak type. The underlying reasons for the successes are discussed and it is concluded that the remaining advances needed in temperature and thermal insulation may well be achieved in new large tokamak experiments now under construction. Comparable progress is being made also in inertial confinement systems; key experiments on achieving the required super-high densities with high-powered pulsed laser systems are about to commence. To achieve fusion reactors will require the combination of three major disciplines: plasma physics, electromechanical engineering and nuclear engineering. Proposals have been made for an international study group to be set up under the IAEA auspices to consider technical objectives and the nature of the next large fusion device which could be constructed internationally, and in which this synthesis could be attempted. (author)

Nuclear fusion an energetic option to the future

International Nuclear Information System (INIS)

Medialdea Utande, A.; Sanchez Sanz, J.

2007-01-01

Nuclear fusion is the energy source of the Sun and the rest of starts. The great availability of deuterium on Earth, the inherent safety of the reactions involved and the intrinsic environmental respect make fusion an attractive energy source for the future of making of man king. International promising contributions are making Fusion Science and Technology progress by leaps and bounds to achieve its long term goal of cost-effective energy-producing plasmas. (Author)

Nuclear measurements, techniques and instrumentation industrial applications plasma physics and nuclear fusion. 1980-1994. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1995-04-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Measurements, Techniques and Instrumentation, with Industrial Applications (of Nuclear Physics and Engineering), and with Plasma Physics and Nuclear Fusion, issued during the period 1980-1994. Most publications are in English. Proceedings of conferences, symposia, and panels of experts may contain some papers in other languages (French, Russian, or Spanish), but all papers have abstracts in English. Price quotes are in Austrian Schillings, do not include local taxes, and are subject to change without notice. Contents cover the three main categories of (i) Nuclear Measurements, Techniques and Instrumentation (Physics, Chemistry, Dosimetry Techniques, Nuclear Analytical Techniques, Research Reactors and Particle Accelerator Applications, Nuclear Data); (ii) Industrial Applications (Radiation Processing, Radiometry, Tracers); and (iii) Plasma Physics and Nuclear Fusion

Nuclear measurements, techniques and instrumentation industrial applications plasma physics and nuclear fusion, 1980-1993. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1994-01-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Measurements, Techniques and Instrumentation, with Industrial Applications (of Nuclear Physics and Engineering), and with Plasma Physics and Nuclear Fusion, issued during the period 1980-1993. Most publications are in English. Proceedings of conferences, symposia, and panels of experts may contain some papers in other languages (French, Russian, or Spanish), but all papers have abstracts in English. Price quotes are in Austrian Schillings, do not include local taxes, and are subject to change without notice. Contents cover the three main categories of (I) Nuclear Measurements, Techniques and Instrumentation (Physics, Chemistry, Dosimetry Techniques, Nuclear Analytical Techniques, Research Reactors and Particle Accelerator Applications, Nuclear Data); (ii) Industrial Applications (Radiation Processing, Radiometry, Tracers); and (iii) Plasma Physics and Nuclear Fusion

Prospects for Tokamak Fusion Reactors

International Nuclear Information System (INIS)

Sheffield, J.; Galambos, J.

1995-01-01

This paper first reviews briefly the status and plans for research in magnetic fusion energy and discusses the prospects for the tokamak magnetic configuration to be the basis for a fusion power plant. Good progress has been made in achieving fusion reactor-level, deuterium-tritium (D-T) plasmas with the production of significant fusion power in the Joint European Torus (up to 2 MW) and the Tokamak Fusion Test Reactor (up to 10 MW) tokamaks. Advances on the technologies of heating, fueling, diagnostics, and materials supported these achievements. The successes have led to the initiation of the design phases of two tokamaks, the International Thermonuclear Experimental Reactor (ITER) and the US Toroidal Physics Experiment (TPX). ITER will demonstrate the controlled ignition and extended bum of D-T plasmas with steady state as an ultimate goal. ITER will further demonstrate technologies essential to a power plant in an integrated system and perform integrated testing of the high heat flux and nuclear components required to use fusion energy for practical purposes. TPX will complement ITER by testing advanced modes of steady-state plasma operation that, coupled with the developments in ITER, will lead to an optimized demonstration power plant

Fusion energy - an abundant energy source for the future

DEFF Research Database (Denmark)

Fusion energy is the fundamental energy source of the Universe, as the energy of the Sun and the stars are produced by fusion of e.g. hydrogen to helium. Fusion energy research is a strongly international endeavor aiming at realizing fusion energy production in power plants on Earth. Reaching...... this goal, mankind will have a sustainable base load energy source with abundant resources, having no CO2 release, and with no longlived radioactive waste. This presentation will describe the basics of fusion energy production and the status and future prospects of the research. Considerations...... of integration into the future electricity system and socio-economic studies of fusion energy will be presented, referring to the programme of Socio-Economic Research on Fusion (SERF) under the European Fusion Energy Agreement (EFDA)....

An integrated approach to the back-end of the fusion materials cycle

International Nuclear Information System (INIS)

Zucchetti, M.; Di Pace, L.; El-Guebaly, L.; Wilson, P.; Kolbasov, B.; Massaut, V.; Pampin, R.

2007-01-01

Within the frame of the International Energy Agency (IEA) Co-operative Program on the Environmental, Safety and Economic Aspects of Fusion Power, an international collaborative study on fusion radioactive waste has been initiated to examine the back-end of the fusion materials cycle as an important stage in maximising the environmental benefits of fusion. The study addresses the management procedures for active materials following the change out of replaceable components and decommissioning of fusion facilities. Numerous differences exist between fission and fusion in terms of activated material type, quantity, activity levels, half-life, radiotoxicity, etc. For fusion, it is important to clearly define the parameters that govern the back-end of the materials cycle. A fusion-specific, unique approach is necessary and needs to be developed. Recycling of materials and clearance (i.e. declassification to non-radioactive material) are the two recommended options for reducing the amount of fusion waste, while disposal as low-level waste (LLW) could be an alternative route for specific materials and components. Both recycling and clearance criteria have been recently revised by national and international institutions. These revisions and their consequences are examined here with applications to selected studies: - Recycling: the important radioactive quantities to be limited are contact dose rate, decay heat, and radioactivity concentration. Handling (hands-on, simple shielded, and remote handling approaches), routing related questions (recycling outside the nuclear industry, recycling in nuclear-specific foundries, other possible recycling scenarios without melting), and other issues (C-14, material impurities) are examined. - Clearance: a definition of a list of nuclides relevant to fusion is made with a proposal of a scenario and a simplified procedure for calculation of a set of fusion-specific clearance limits. - Disposal: a proposal of a generalized definition of

20th IAEA fusion energy conference 2004. Conference proceedings

International Nuclear Information System (INIS)

2005-01-01

The 20th International Atomic Energy Agency (IAEA) Fusion Energy Conference (FEC) was held in Vilamoura, Portugal, from 1 to 6 November 2004. The Instituto Superior Tecnico through the Centro de Fusao Nuclear on behalf of the Portuguese Government and the Association EURATOM/IST hosted the conference. The IAEA wishes to express its gratitude to the host. More than 600 delegates representing 33 countries and three international organizations attended the Fusion Energy Conference 2004. The Programme Committee accepted a total of some 437 papers for presentation at the conference. The scientific experimental and theoretical papers have been grouped with respect to the following themes: Overview on magnetic and inertial fusion; Advanced Scenarios and Steady State; Edge Localized Modes; Fusion Technology; Transport Theory; Beta Limits; Hybrid Scenarios; H-mode and Transport; ITER; Alfven Modes and Wave Heating; Operational Limits and Momentum Transport; Energetic Particles and Stability; Neoclassical Tearing Modes; Transport and Turbulence; Inertial Fusion; Configuration Effects and Transport; and Plasma-wall Interaction. The conference adjourned with the announcement of the next IAEA Fusion Energy Conference, which will be held for the first time in the People's Republic of China, in the city of Chengdu, October 16-22, 2006

Agreement on the privileges and immunities of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project. Latest status. Declarations/reservations

International Nuclear Information System (INIS)

2007-01-01

The Agreement on the Privileges and Immunities of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project, for which the Director General of the IAEA is depositary, was done in Paris on 21 November 2006. Pursuant to Article 25 thereof, the Agreement on the Privileges and Immunities of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project 'shall enter into force thirty days after the deposit of instruments of ratification, acceptance or approval of this Agreement by the People's Republic of China, EURATOM, the Republic of India, Japan, the Republic of Korea and the Russian Federation.' The text of the Agreement is reproduced in the Annex hereto for the information of all Member States

ITER: the first experimental fusion reactor

International Nuclear Information System (INIS)

Rebut, P.H.

1995-01-01

The International Thermonuclear Experimental Reactor (ITER) project is a multiphased project, at present proceeding under the auspices of the International Atomic Energy Agency according to the terms of a four-party agreement between the European Atomic Energy Community, the Government of Japan, the Government of the USA and the Government of Russia (''the parties''). The project is based on the tokamak, a Russian invention which has been brought to a high level of development and progress in all major fusion programs throughout the world.The objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for commercial energy production and to test technologies for a demonstration fusion power plant. During the extended performance phase of ITER, it will demonstrate the characteristics of a fusion power plant, producing more than 1500MW of fusion power.The objective of the engineering design activity (EDA) phase is to produce a detailed, complete and fully integrated engineering design of ITER and all technical data necessary for the future decision on the construction of ITER.The ITER device will be a major step from present fusion experiments and will encompass all the major elements required for a fusion reactor. It will also require the development and the implementation of major new components and technologies.The inside surface of the plasma containment chamber will be designed to withstand temperature of up to 500 C, although normal operating temperatures will be substantially lower. Materials will have to be carefully chosen to withstand these temperatures, and a high neutron flux. In addition, other components of the device will be composed of state-of-the-art metal alloys, ceramics and composites, many of which are now in the early stage of development of testing. (orig.)

Bouillabaisse sushi fusion power

CERN Multimedia

2004-01-01

"If avant-garde cuisine is any guide, Japanese-French fusion does not work all that well. And the interminable discussions over the International Thermonuclear Experimental Reactor (ITER) suggest that what is true of cooking is true of physics" (1 page)

Treatment of Spinal Tuberculosis by Debridement, Interbody Fusion and Internal Fixation via Posterior Approach Only.

Science.gov (United States)

Tang, Ming-xing; Zhang, Hong-qi; Wang, Yu-xiang; Guo, Chao-feng; Liu, Jin-yang

2016-02-01

Surgical treatment for spinal tuberculosis includes focal tuberculosis debridement, segmental stability reconstruction, neural decompression and kyphotic deformity correction. For the lesions mainly involved anterior and middle column of the spine, anterior operation of debridement and fusion with internal fixation has been becoming the most frequently used surgical technique for the spinal tuberculosis. However, high risk of structural damage might relate with anterior surgery, such as damage in lungs, heart, kidney, ureter and bowel, and the deformity correction is also limited. Due to the organs are in the front of spine, there are less complications in posterior approach. Spinal pedicle screw passes through the spinal three-column structure, which provides more powerful orthopedic forces compared with the vertebral body screw, and the kyphotic deformity correction effect is better in posterior approach. In this paper, we report a 68-year-old male patient with thoracic tuberculosis who underwent surgical treatment by debridement, interbody fusion and internal fixation via posterior approach only. The patient was placed in prone position under general anesthesia. Posterior midline incision was performed, and the posterior spinal construction was exposed. Then place pedicle screw, and fix one side rod temporarily. Make the side of more bone destruction and larger abscess as lesion debridement side. Resect the unilateral facet joint, and retain contralateral structure integrity. Protect the spinal cord, nerve root. Clear sequestrum, necrotic tissue, abscess of paravertebral and intervertebral space. Specially designed titanium mesh cages or bone blocks were implanted into interbody. Fix both side rods and compress both sides to make the mesh cages and bone blocks tight. Reconstruct posterior column structure with allogeneic bone and autologous bone. Using this technique, the procedures of debridement, spinal cord decompression, deformity correction, bone grafting

21. IAEA fusion energy conference. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Recognizing the prominent role that nuclear energy plays in the world, and based on the expectation that nuclear fusion will be able to provide an abundant source of energy, the International Atomic Energy Agency (IAEA) supports the exchange of scientific and technical information on fusion research through conferences, meetings and projects. The 21st IAEA Fusion Energy Conference (FEC 2006) provided a forum for presenting and discussing the progress that is being made in fusion experiments, theory and technological developments. It is expected that the progress in the establishment of ITER since the last Fusion Energy Conference will put more emphasis on the physics and technology R and D aspects in the realization of fusion as a clean and lasting energy source. FEC 2006 covered the following topics: OV Overviews; EX Magnetic Confinement Experiments; TH Magnetic Confinement Theory and Modelling; IT ITER Activities; IF Inertial Fusion Experiments and Theory; IC Innovative Concepts; FT Fusion Technology and Power Plant Design; SE Safety, Environmental and Economic Aspects of Fusion. At the same time, a series of satellite meetings and fusion related exhibitions took place.

Development of fusion safety standards

International Nuclear Information System (INIS)

Longhurst, G.R.; Petti, D.A.; Dinneen, G.A.; Herring, J.S.; DeLooper, J.; Levine, J.D.; Gouge, M.J.

1996-01-01

Two new U.S. Department of Energy (DOE) standards have been prepared to assist in the design and regulation of magnetic fusion facilities. They are DOE-STD-6002-96, 'Safety of Magnetic Fusion Facilities - Requirements,' and DOE-STD-6003-96 'Safety of Magnetic Fusion Facilities - Guidance.' The first standard sets forth requirements, mostly based on the Code of Federal Regulations, deemed necessary for the safe design and operation of fusion facilities and a set of safety principles to use in the design. The second standard provides guidance on how to meet the requirements identified in DOE-STD-6002-96. It is written specifically for a facility such as the International Thermonuclear Experimental Reactor (ITER) in the DOE regulatory environment. As technical standards, they are applicable only to the extent that compliance with these standards is included in the contracts of the developers. 7 refs., 1 fig

Fusion power: Expected environmental characteristics and status of R and D

International Nuclear Information System (INIS)

Fowler, T.K.

1989-01-01

From the outset in the 1950's, fusion research has been motivated by environmental concerns as well as long-term fuel supply issues. Compared to fossil fuels both fusion and fission would produce essentially zero emissions to the atmosphere. Compared to fission, fusion reactors should offer high demonstrability of public protection from accidents and a substantial amelioration of the radioactive waste problem. Fusion still requires lengthy development, the earliest commercial deployment being likely to occur around 2025-2050. However, steady scientific progress is being made and there is a wide consensus that it is time to plan large-scale engineering development. A major international effort, called the International Thermonuclear Experimental Reactor (ITER), is being carried out under IAEA auspices to design the world's first fusion engineering test reactor, which could be constructed in the 1990's. 5 figs., 3 tabs

Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell

CERN Document Server

Esposito, B; Maruccia, G; Petrizzi, L; Bignon, G; Blandin, C; Chauffriat, S; Lebrun, A; Recroix, H; Trapp, J P; Kaschuck, Y

2000-01-01

The international fusion materials irradiation facility (IFMIF) project deals with the study of an accelerator-based, deuterium-lithium source, producing high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials for fusion energy reactors. IFMIF would also provide calibration and validation of data from fission reactor and other accelerator based irradiation tests. This paper describes the activity on neutron/gamma dosimetry (necessary for the characterization of the specimens' irradiation) performed in the frame of the IFMIF conceptual design evaluation (CDE) neutronics tasks. During the previous phase (conceptual design activity (CDA)) the multifoil activation method was proposed for the measurement of the neutron fluence and spectrum and a set of suitable foils was defined. The cross section variances and covariances of this set of foils have now been used for tests on the sensitivity of the IFMIF neutron spectrum determination to cross section uncertainties...

International bulletin on atomic and molecular data for fusion. No. 60

International Nuclear Information System (INIS)

Stephens, J.A.; Bannister, M.E.; Delcroix, J.L.; Fuhr, J.

2001-06-01

This bulletin comprises updated atomic and molecular data for fusion. It includes the Atomic and Molecular Data Information System (AMDIS) of the IAEA. It contains two parts: a bibliographic database for atomic and molecular data for fusion research, and numerical databases of recommended and evaluated atomic, molecular and plasma-surface interaction data. The indexed papers are also listed separately for structure and spectra, atomic and molecular collisions, and surface interactions

Fusion energy for the 21st century

International Nuclear Information System (INIS)

Harris, J.H.

1999-01-01

Fusion reactions like those that power the stars have the potential of providing bulk electricity generation with reduced emissions and low radioactive hazard, but pose many challenges in physics and technology. The H-1 Heliac Major National Research Facility now being developed offers Australian scientists and engineers an opportunity to participate in the collaborative international fusion research program. Work on H-1NF contributes not only to the realisation of fusion power, but offers the stimulus and opportunity for advanced training and the development of spin-off technology

Safety of magnetic fusion facilities: Guidance

International Nuclear Information System (INIS)

1996-05-01

This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities

Strategic plan for the restructured US fusion energy sciences program

International Nuclear Information System (INIS)

1996-08-01

This plan reflects a transition to a restructured fusion program, with a change in focus from an energy technology development program to a fusion energy sciences program. Since the energy crisis of the early 1970's, the U.S. fusion program has presented itself as a goal- oriented fusion energy development program, with milestones that required rapidly increasing budgets. The Energy Policy Act of 1992 also called for a goal-oriented development program consistent with the Department's planning. Actual funding levels, however, have forced a premature narrowing of the program to the tokamak approach. By 1995, with no clear, immediate need driving the schedule for developing fusion energy and with enormous pressure to reduce discretionary spending, Congress cut fusion program funding for FY 1996 by one-third and called for a major restructuring of the program. Based on the recommendations of the Fusion Energy Advisory Committee (FEAC), the Department has decided to pursue a program that concentrates on world-class plasma, science, and on maintaining an involvement in fusion energy science through international collaboration. At the same time, the Japanese and Europeans, with energy situations different from ours, are continuing with their goal- oriented fusion programs. Collaboration with them provides a highly leveraged means of continued involvement in fusion energy science and technology, especially through participation in the engineering and design activities of the International Thermonuclear Experimental Reactor program, ITER. This restructured fusion energy sciences program, with its focus on fundamental fusion science and technology, may well provide insights that lead to more attractive fusion power plants, and will make use of the scientific infrastructure that will allow the United States to launch a fusion energy development program at some future date

Fusion Canada issue 29

International Nuclear Information System (INIS)

1995-10-01

A short bulletin from the National Fusion Program highlighting in this issue Canada-Europe Accords: 5 year R and D collaboration for the International Thermonuclear Experimental Reactor (ITER) AECL is designated to arrange and implement the Memorandum of Understanding (MOU) and the ITER Engineering Design Activities (EDA) while EUROTAM is responsible for operating Europe's Fusion R and D programs plus MOU and EDA. The MOU includes tokamaks, plasma physics, fusion technology, fusion fuels and other approaches to fusion energy (as alternatives to tokamaks). STOR-M Tokamak was restarted at the University of Saskatchewan following upgrades to the plasma chamber to accommodate the Compact Toroid (CT) injector. The CT injector has a flexible attachment thus allowing for injection angle adjustments. Real-time video images of a single plasma discharge on TdeV showing that as the plasma density increases, in a linear ramp divertor, the plasma contact with the horizontal plate decreases while contact increases with the oblique plate. Damage-resistant diffractive optical elements (DOE) have been developed for Inertial Confinement Fusion (ICF) research by Gentac Inc. and the National Optics Institute, laser beam homogeniser and laser harmonic separator DOE can also be made using the same technology. Studies using TdeV indicate that a divertor will be able to pump helium from the tokamak with a detached-plasma divertor but helium extraction performance must first be improved, presently the deuterium:helium retention radio-indicates that in order to pump enough helium through a fusion reactor, too much deuterium-tritium fuel would be pumped out. 2 fig

Fusion Simulation Program

International Nuclear Information System (INIS)

Greenwald, Martin

2011-01-01

Many others in the fusion energy and advanced scientific computing communities participated in the development of this plan. The core planning team is grateful for their important contributions. This summary is meant as a quick overview the Fusion Simulation Program's (FSP's) purpose and intentions. There are several additional documents referenced within this one and all are supplemental or flow down from this Program Plan. The overall science goal of the DOE Office of Fusion Energy Sciences (FES) Fusion Simulation Program (FSP) is to develop predictive simulation capability for magnetically confined fusion plasmas at an unprecedented level of integration and fidelity. This will directly support and enable effective U.S. participation in International Thermonuclear Experimental Reactor (ITER) research and the overall mission of delivering practical fusion energy. The FSP will address a rich set of scientific issues together with experimental programs, producing validated integrated physics results. This is very well aligned with the mission of the ITER Organization to coordinate with its members the integrated modeling and control of fusion plasmas, including benchmarking and validation activities. (1). Initial FSP research will focus on two critical Integrated Science Application (ISA) areas: ISA1, the plasma edge; and ISA2, whole device modeling (WDM) including disruption avoidance. The first of these problems involves the narrow plasma boundary layer and its complex interactions with the plasma core and the surrounding material wall. The second requires development of a computationally tractable, but comprehensive model that describes all equilibrium and dynamic processes at a sufficient level of detail to provide useful prediction of the temporal evolution of fusion plasma experiments. The initial driver for the whole device model will be prediction and avoidance of discharge-terminating disruptions, especially at high performance, which are a critical

Plasma physics and controlled nuclear fusion research 1988. V.3

International Nuclear Information System (INIS)

1989-01-01

Volume 3 of the proceedings of the twelfth international conference on plasma physics and controlled nuclear fusion, held in Nice, France, 12-19 October, 1988, contains papers presented on inertial fusion. Direct and indirect laser implosion experiments, programs of laser construction, computer modelling of implosions and resulting plasmas, and light ion beam fusion experiments are discussed. Refs, figs and tabs

Fusion in computer vision understanding complex visual content

CERN Document Server

Ionescu, Bogdan; Piatrik, Tomas

2014-01-01

This book presents a thorough overview of fusion in computer vision, from an interdisciplinary and multi-application viewpoint, describing successful approaches, evaluated in the context of international benchmarks that model realistic use cases. Features: examines late fusion approaches for concept recognition in images and videos; describes the interpretation of visual content by incorporating models of the human visual system with content understanding methods; investigates the fusion of multi-modal features of different semantic levels, as well as results of semantic concept detections, fo

Past, present and future of the fusion reactors

International Nuclear Information System (INIS)

Rosenbaum P, M.

1992-01-01

Among the alternate technologies that have acquired a special interest in the present decade, we find the nuclear fusion. Within this, the fusion reactors by magnetic confinement of the Tokamak type have shown an increasing technological progress during this period. For this reason, a new strategy, coordinated at international level, has been implemented for the specific development of the nuclear fusion reactors, aimed to face those scientific and technological aspects which still remain, and which will determine their future economic feasibility. (Author)

Tritium accountancy in fusion systems

Energy Technology Data Exchange (ETDEWEB)

Klein, J.E.; Clark, E.A.; Harvel, C.D.; Farmer, D.A.; Tovo, L.L.; Poore, A.S. [Savannah River National Laboratory, Aiken, SC (United States); Moore, M.L. [Savannah River Nuclear Solutions, Aiken, SC (United States)

2015-03-15

The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MCA) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MCA requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBA) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material sub-accounts (MSA) are established along with key measurement points (KMP) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSA. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breeding, burn-up, and retention of tritium in the fusion device. The concept of 'net' tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines. (authors)

Estimates of external dose-rate conversion factors and internal dose conversion factors for selected radionuclides released from fusion facilities

Energy Technology Data Exchange (ETDEWEB)

Homma, Toshimitsu; Togawa, Orihiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-11-01

This report provides a tabulation of both external dose-rate conversion factors and internal dose conversion factors using radioactive decay data in the updated Evaluated Nuclear Structure Data File (ENSDF) for selected 26 radionuclides and all their daughter radionuclides of potential importance in safety assessments of fusion facilities. The external dose-rate conversion factors for 21 target organs are tabulated for three exposure modes that are immersion in contaminated air, irradiation at a height of 1 m above a contaminated ground surface and immersion contaminated water. For internal exposure, committed dose equivalents, based on the methodology of ICRP Publication 30, in the same target organs per intake of unit activity are given for the inhalation and ingestion exposure pathways. The data presented here is intended to be generally used for safety assessments of fusion reactors. Comparisons of external effective dose-rate conversion factors and committed effective dose equivalents are made with the previous data from the independent data bases to provide quality assurance on our calculated results. There is generally good agreement among data from the independent data bases. The differences in the values of both effective dose-rate and dose conversion factors appeared are primarily due to differences in calculational methodology, the use of different radioactive decay data, and compilation errors. (author)

Staged deployment of the International Fusion Materials Irradiation Facility

International Nuclear Information System (INIS)

Takeuchi, H.; Sugimoto, M.; Nakamura, H.

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation ( 2MW/m 2 at 500cm 3 ) to obtain engineering data for potential DEMO materials under irradiation up to 100-200 dpa. In summary, the new, reduced cost IFMIF design and staged deployment still satisfies the original mission. The estimated cost of the 1st Stage facility is only $303.6 M making it financially much more attractive. Currently, IFMIF Key Element Technology Phase (KEP) is underway to reduce the key technology risk factors. (author)

Accelerator aspects of heavy ion induced inertial fusion

Energy Technology Data Exchange (ETDEWEB)

Boehme, D

1983-01-01

Besides the possibilities of the magnetic fusion those of inertial fusion have increasingly found interest. Bundled photon and corpuscular beams shall be symetrically focussed from the outside on a pellet with the fusion fuel being compressed far beyond the density of the ordinary solids. Laser, light ion and heavy ion beams can be used as driver beams. The GSI took over the project leadership for a five years' research programme with formulated questions on heavy ion fusion. The project is promoted by the BMFT. During the international symposium the opportunity of intensive discussions on research work in this field in different countries was made use of.

Stellarator fusion neutronics research in Australia

International Nuclear Information System (INIS)

Zimin, S.; Cross, R.C.

1997-01-01

The new status of the H-INF Heliac Stellaralor as a National Facility and the signed international Implementing Agreement on 'Collaboration in the Development of the Stellarator Concept' represents a significant encouragement for further fusion research in Australia. In this report the future of fusion research in Australia is discussed with special attention being paid to the importance of Stellarator power plant studies and in particular stellarator fusion neutronics. The main differences between tokamak and stellarator neutronics analyses are identified, namely the neutron wall loading, geometrical modelling and total heating in in-vessel reactor components including toroidal field (TF) coils. Due to the more complicated nature of stellarator neutronics analyses, simplified approaches to fusion neutronics already developed for tokamaks are expected to be even more important and widely used for designing a Conceptual Stellarator Power Plant

Thermal Studies of the Laser Inertial Fusion Energy (LIFE) Target during Injection into the Fusion Chamber

Energy Technology Data Exchange (ETDEWEB)

Miles, R. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Havstad, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); LeBlanc, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chang, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Golosker, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rosso, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-09-09

The tests of the external heat transfer coefficient suggests that the values used in the numerical analysis for the temperature distribution within the fusion fuel target following flight into the target chamber are probably valid. The tests of the heat transfer phenomena occurring within the target due the rapid heating of the LEH window for the hot gasses within the fusion chamber show that the heat does indeed convect via the internal helium environment of the target towards the capsule and that the pressure in the front compartment of the target adjacent to the LEH window increases such that t bypass venting of the internal helium into the second chamber adjacent to the capsule is needed to prevent rupture of the membranes. The bypass flow is cooled by the hohlraum during this venting. However, the experiments suggest that our internal heat flow calculations may be low by about a factor of 2. Further studies need to be conducted to investigate the differences between the experiment and the numerical analysis. Future studies could also possibly bring the test conditions closer to those expected in the fusion chamber to better validate the results. A sacrificial layer will probably be required on the LEH window of the target and this can be used to mitigate any unexpected target heating.

Magnetic fusion development for global warming suppression

International Nuclear Information System (INIS)

Li Jiangang; Zhang Jie; Duan Xuru

2010-01-01

Energy shortage and environmental pollution are two critical issues for human beings in the 21st century. There is an urgent need for new sustainable energy to meet the fast growing demand for clean energy. Fusion is one of the few options which may be able to satisfy the requirement for large scale sustainable energy generation and global warming suppression and therefore must be developed as quickly as possible. Fusion research has been carried out for the past 50 years. It is too long to wait for another 50 years to generate electricity by fusion. A much more aggressive approach should be taken with international collaboration towards the early use of fusion energy to meet the urgent needs for energy and global warming suppression.

Fusion is urgent needed for the developing countries

International Nuclear Information System (INIS)

Li Jiangang

2005-01-01

Energy is a global problem, as it is central to economic development, climate and environment, and international stability and sustainability. Energy need is expected to double in 40 years and an even larger increase is needed to lift the world out of poverty. 80% of world's energy is generated by burning fossil fuels, which is driving climate change and generating pollution. China will grow up to be a moderate developed country in 2050. The coal-centred energy structure will remain until 2050. Annual Energy Consumption per person will increase from near 1 TCE to no less than 3 TCE ( at present time, US: 11.5 TCE; West Europe: 5.6 TCE; Japan: 5.1 TCE) Estimated Energy Demand: increasing from near 1B TCE to over 4B TCE within next 3-4 decades. To realize the long-term sustainable development, it is necessary for China to explore reliable ways and develop thousands of GW non- fossil fuel power. The fission energy is a transit solution. To build hundreds of GW Fission Nuclear Power Plants in China - social problems, safety and environmental concerns, technical difficulties should be solved in near future. It is crucial and urgent for China to realize the controlled Nuclear Fusion Energy for our long-term development in the future as early as possible. Fusion shows environmentally responsible and intrinsically safe, the supplies of fuel are essentially limitless. JET has produced 16MW of fusion power and shown that fusion can be mastered on earth. Fusion has a long and successful history of international collaboration with obvious benefits to all partners for peaceful purpose. ITER is a device for us to bring the Sun to earth for the first time in the history. A properly organised and funded fusion development programme could lead to a proto-type fusion power plant to generate electricity to the grid within about 30 years (ITER+IFMIF). For developing countries, such as China and India, fusion is one of the very few options for large-scale sustainable energy generation

The status of beryllium technology for fusion

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Longhurst, G.R. E-mail: gx1@inel.gov; Shestakov, V.; Kawamura, H

2000-12-01

Beryllium was used for a number of years in the Joint European Torus (JET), and it is planned to be used extensively on the lower heat-flux surfaces of the reduced technical objective/reduced cost international thermonuclear experimental reactor (RTO/RC ITER). It has been included in various forms in a number of tritium breeding blanket designs. There are technical advantages but also a number of safety issues associated with the use of beryllium. Research in a variety of technical areas in recent years has revealed interesting issues concerning the use of beryllium in fusion. Progress in this research has been presented at a series of International Workshops on Beryllium Technology for Fusion. The most recent workshop was held in Karlsruhe, Germany on 15-17 September 1999. In this paper, a summary of findings presented there and their implications for the use of beryllium in the development of fusion reactors are presented.

The status of beryllium technology for fusion

International Nuclear Information System (INIS)

Scaffidi-Argentina, F.; Longhurst, G.R.; Shestakov, V.; Kawamura, H.

2000-01-01

Beryllium was used for a number of years in the Joint European Torus (JET), and it is planned to be used extensively on the lower heat-flux surfaces of the reduced technical objective/reduced cost international thermonuclear experimental reactor (RTO/RC ITER). It has been included in various forms in a number of tritium breeding blanket designs. There are technical advantages but also a number of safety issues associated with the use of beryllium. Research in a variety of technical areas in recent years has revealed interesting issues concerning the use of beryllium in fusion. Progress in this research has been presented at a series of International Workshops on Beryllium Technology for Fusion. The most recent workshop was held in Karlsruhe, Germany on 15-17 September 1999. In this paper, a summary of findings presented there and their implications for the use of beryllium in the development of fusion reactors are presented

Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

1995-12-01

This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

EU socio-economic research on fusion: findings and program

International Nuclear Information System (INIS)

Tosato, G.C.

2002-01-01

In 1997 the European Commission launched a Socio-Economic Research program to study under which conditions future fusion power plants may become competitive, compatible with the energy supply system and acceptable for the public. The program is developed by independent experts making use of well established international methodologies. It has been shown, among others, that: 1) local communities are ready to support the construction of an experimental fusion facility, if appropriate communication and awareness campaigns are carried out; 2) since the externalities are much lower than for competitors, fusion power plants may become the major producer of base load electricity at the end of the century in Europe, if climate changes have to be mitigated, if the construction of new nuclear fission power plants continues to be constrained and if nuclear fusion power plants become commercially available in 2050. Cooperating with major international organizations, the program for next year aims to demonstrate that the potential global benefits of fusion power plants in the second half of the century largely outdo the RD and D costs borne in the first half to make it available. (author)

Numerical studies of deuterium-tritium ignition in impact-fusion targets

International Nuclear Information System (INIS)

Zubrin, R.M.; Ribe, F.L.

1989-01-01

A numerical one-dimensional solution of the Euler equations for an imploding spherical tungsten shell with internal deuterium-tritium gas is applied to study impact-fusion dynamics with parameters of fusion reactor relevance. Thermal conduction and radiative energy loss by the plasma are taken into account, as is heating by fusion generated alpha particles. A variety of target sizes and impact velocities are examined, and scaling laws for fusion yields are deduced which define possible parameters for conceptual commercial impact-fusion power reactors. It is found that shell energies and velocities of about 30 MJ and 110 km/s would be satisfactory. A commercial impact-fusion reactor based on such parameters is discussed

Fusion rings and fusion ideals

DEFF Research Database (Denmark)

Andersen, Troels Bak

by the so-called fusion ideals. The fusion rings of Wess-Zumino-Witten models have been widely studied and are well understood in terms of precise combinatorial descriptions and explicit generating sets of the fusion ideals. They also appear in another, more general, setting via tilting modules for quantum......This dissertation investigates fusion rings, which are Grothendieck groups of rigid, monoidal, semisimple, abelian categories. Special interest is in rational fusion rings, i.e., fusion rings which admit a finite basis, for as commutative rings they may be presented as quotients of polynomial rings...

Genetically Controlled Fusion, Exocytosis and Fission of Artificial Vesicles

DEFF Research Database (Denmark)

Bönzli, Eva; Hadorn, Maik; De Lucrezia, Davide

if a special class of viral proteins, termed fusogenic peptides, were added to the external medium. In the present work, we intend to develop genetically controlled fusion, fission and exocytosis of vesicles by the synthesis of peptides within vesicles. First, we enclosed synthesized peptides in vesicles...... to induce in a next step fusion of adjacent vesicles, fission and exocytosis of nested vesicles. Second, we will replace the peptides by an enclosed cell-free expression system to internally synthesize fusion peptides. To control the gene expression, different mechanisms are available, e.g. addition...... fusion, fission and exocytosis....

Congress turns cold on fusion

International Nuclear Information System (INIS)

Marshall, E.

1984-01-01

A 5% cut in fusion research budgets will force some programs to be dropped in order to keep the large machinery running unless US and European scientists collaborate instead of competing. Legislators became uneasy about the escalating costs of the new devices. The 1984 budget of $470 million for magnetic fusion research is only half the projected cost of the Tokomak Fusion Core Experiment (TFCX) planned to ignite, for the first time, a self-sustaining burn. Planning for the TCFX continued despite the message from Congress. Work at the large institutions at Princeton, MIT, etc. may survive at the expense of other programs, some of which will lose academic programs as well. Scientists point to the loss of new ideas and approaches when projects are cancelled. Enthusiasm is growing for international collaboration

International bulletin on atomic and molecular data for fusion. No. 17

International Nuclear Information System (INIS)

Katsonis, K.; Langley, R.A.

1981-11-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported: Electron ionization cross sections for light elements, single electron capture by highly charged ions colliding with hydrogen, inconel 626 surface exfoliation, cavities in nickel induced by helium ion irradiation, electron impact excitation of hydrogenic ions. The bulletin contains a list of references for the publications on controlled fusion and plasma physics for 1980 and 1981

Fusion Plasma Physics and ITER - An Introduction (2/4)

CERN Multimedia

CERN. Geneva

2011-01-01

The second lecture will explore some of the key physics phenomena which govern the behaviour of magnetic fusion plasmas and which have been the subject of intense research during the past 50 years: plasma confinement, magnetohydrodynamic stability and plasma-wall interactions encompass the major areas of plasma physics which must be understood to assemble an overall description of fusion plasma behaviour. In addition, as fusion plasmas approach the “burning plasma” regime, where internal heating due to fusion products dominates other forms of heating, the physics of the interaction between the α-particles produced by D-T fusion reactions and the thermal “background” plasma becomes significant. This lecture will also introduce the basic physics of fusion plasma production, plasma heating and current drive, and plasma measurements (“diagnostics”).

Bubble fusion: Preliminary estimates

International Nuclear Information System (INIS)

Krakowski, R.A.

1995-01-01

The collapse of a gas-filled bubble in disequilibrium (i.e., internal pressure much-lt external pressure) can occur with a significant focusing of energy onto the entrapped gas in the form of pressure-volume work and/or acoustical shocks; the resulting heating can be sufficient to cause ionization and the emission of atomic radiations. The suggestion that extreme conditions necessary for thermonuclear fusion to occur may be possible has been examined parametrically in terms of the ratio of initial bubble pressure relative to that required for equilibrium. In this sense, the disequilibrium bubble is viewed as a three-dimensional ''sling shot'' that is ''loaded'' to an extent allowed by the maximum level of disequilibrium that can stably be achieved. Values of this disequilibrium ratio in the range 10 -5 --10 -6 are predicted by an idealized bubble-dynamics model as necessary to achieve conditions where nuclear fusion of deuterium-tritium might be observed. Harmonic and aharmonic pressurizations/decompressions are examined as means to achieve the required levels of disequilibrium required to create fusion conditions. A number of phenomena not included in the analysis reported herein could enhance or reduce the small levels of nuclear fusions predicted

Intense neutron irradiation facility for fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

Noda, Kenji; Oyama, Yukio; Kato, Yoshio; Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

Technical R and D of d-Li stripping type neutron irradiation facilities for development of fusion reactor materials was carried out in Fusion Materials Irradiation Test Facility (FMIT) project and Energy Selective Neutron Irradiation Test Facility (ESNIT) program. Conceptual design activity (CDA) of International Fusion Materials Irradiation Facility (IFMIF), of which concept is an advanced version of FMIT and ESNIT concepts, are being performed. Progress of users` requirements and characteristics of irradiation fields in such neutron irradiation facilities, and outline of baseline conceptual design of IFMIF were described. (author)

The DD Cold Fusion-Transmutation Connection

Science.gov (United States)

Chubb, Talbot A.

2005-12-01

LENR theory must explain dd fusion, alpha-addition transmutations, radiationless nuclear reactions, and three-body nuclear particle reactions. Reaction without radiation requires many-body D Bloch+ periodicity in both location and internal structure dependencies. Electron scattering leads to mixed quantum states. The radiationless dd fusion reaction is 2-D Bloch+ -> {}4 He Bloch2+. Overlap between {}4 He Bloch2+ and surface Cs leads to alpha absorption. In the Iwamura et al. studies active deuterium is created by scattering at diffusion barriers.

Finnish Fusion Research Programme Yearbook 1993-1994

International Nuclear Information System (INIS)

Karttunen, S.; Paettikangas, T.

1995-05-01

Finnish Fusion Research Programme (FFUSION) is one of the national energy research programmes funded by the Ministry of Trade and Industry and from 1995 by TEKES. National organization for fusion research is necessary for efficient and successful participation in international fusion programmes. FFUSION programme serves well for this purpose and it made possible to establish relations and the dialogue with the European Fusion Programme. The process led to the Finnish Association Euratom-TEKES in early 1995. The first period of the FFUSION programme (1993-1994) was preparation for the association to the Community Programme. The strategy was to emphasize fusion technology parallel with the basic fusion and plasma physics and to activate the related Finnish industry to collaborate and participate in the FFUSION programme and later in the European Fusion Programme. The key element in the strategy is the focusing our fairly small R and D effort to a few topics, which increases possibilities to be competitive in Europe. The physics programme in FFUSION deals mainly with theoretical and computational studies of radio-frequency heating in tokamak plasmas. Technology programme started with prestudies in 1993 and it concentrates into two areas: fusion reactor materials and remote handling systems. (8 figs., 3 tabs.)

International bulletin on atomic and molecular data for fusion. No. 47

International Nuclear Information System (INIS)

Botero, J.

1993-12-01

This bulletin, published by the IAEA, provides atomic and molecular data references relevant to fusion research and technology. In part I the indexation of the papers is provided separately for (i) structure and spectra, (ii) atomic and molecular collisions, and (iii) surface interactions. Part II contains the bibliographic data for the above-listed topics and for high-energy laser and beam-matter interaction of atomic particles with fields. Also included are sections on atomic and molecular data needs for fusion research and on news about ALADDIN (A Labelled Atomic Data INterface) and evaluated data bases

Goals, challenges, and successes of managing fusion activated materials

International Nuclear Information System (INIS)

El-Guebaly, L.; Massaut, V.; Tobita, K.; Cadwallader, L.

2008-01-01

After decades of designing magnetic and inertial fusion power plants, it is timely to develop a new framework for managing the activated (and contaminated) materials that will be generated during plant operation and after decommissioning-a framework that takes into account the lessons learned from numerous international fusion and fission studies and the environmental, political, and present reality in the U.S., Europe, and Japan. This will clearly demonstrate that designers developing fusion facilities will be dealing with the back end of this type of energy production from the beginning of the conceptual design of power plants. It is becoming evident that future regulations for geological burial will be upgraded to assure tighter environmental controls. Along with the political difficulty of constructing new repositories worldwide, the current reality suggests reshaping all aspects of handling the continual stream of fusion active materials. Beginning in the mid 1980s and continuing to the present, numerous fusion designs examined replacing the disposal option with more environmentally attractive approaches, redirecting their attention to recycling and clearance while continuing the development of materials with low activation potential. There is a growing international effort in support of this new trend. In this paper, recent history is analyzed, a new fusion waste management scheme is covered, and possibilities for how its prospects can be improved are examined

Fusion program overview

International Nuclear Information System (INIS)

Clarke, J.F.

1983-01-01

There has been and continues to be a perceived need for the fusion energy option in our energy future. The National Energy Plan states that ''the Federal Government recognizes a direct responsibility to demonstrate the scientific and engineering feasibility of fusion''. The goal of the program, in exercising this responsibility, is to develop the knowledge base upon which decisions on the commercial feasibility of fusion will be made after the conclusion of the present scientific feasibility phase of the program. The strategy is to preceed sequentially through a product definition phase, to the product development phase. Product definition is the identification of an attractive fusion reactor concept supported by a sound base of scientific and technological information. Product development is the further refinement of scientific, technological and engineering information base of the selected concept to provide a firm basis for commercial application. Each of these phases will be discussed with special emphasis on the relationship between the annual appropriation process and the influence of external forces on the pace of the program. This discussion will include the use of international cooperation to maintain and extend program scope. Further discussion will cover the important scientific and technological advances of the last few years and the way in which they have influenced the development of our management strategy to maximize our resources

Fusion technology 1998

International Nuclear Information System (INIS)

Beaumont, B.; Libeyre, P.; Gentile, B. de; Tonon, G.

1998-01-01

The Symposium On Fusion Technology (SOFT) is held every two years with the objective to set the stage for the exchange of information on the design, construction and operation of fusion experiments and on the technology which is being developed for the next step devices and fusion reactors. By decision of the International Organizing Committee, the 20. SOFT includes invited talks, and oral and poster contributions in the following topics: plasma facing components, plasma heating and current drive, plasma engineering and control, experimental systems and diagnostics, magnets and power supplies, fuel technologies, remote operation, blanket and shield technologies, safety and environment, and system engineering and future devices. This symposium differs from the previous ones of this series by the way the present proceedings are produced. In order to have the written material available to the participants and the community at the nearest to the conference event, the papers have been collected 2 months in advance and printed in the present books. The goal was to deliver them to each participant upon arrival to the conference centre. These books contain all the papers corresponding to poster presentation, and the abstracts of the oral contributions and invited papers. The papers corresponding to these presentations, both oral and invited, will be published in 1999, after a standard review process, in a supplement of Fusion Engineering and Design. (author)

Implications of fusion power plant studies for materials requirements

International Nuclear Information System (INIS)

Cook, Ian; Ward, David; Dudarev, Sergei

2002-01-01

This paper addresses the key requirements for fusion materials, as these have emerged from studies of commercial fusion power plants. The objective of the international fusion programme is the creation of power stations that will have very attractive safety and environmental features and viable economics. Fusion power plant studies have shown that these objectives may be achieved without requiring extreme advances in materials. But it is required that existing candidate materials perform at least as well as envisaged in the environment of fusion neutrons, heat fluxes and particle fluxes. The development of advanced materials would bring further benefits. The work required entails the investigation of many intellectually exciting physics issues of great scientific interest, and of wider application than fusion. In addition to giving an overview, selected aspects of the science, of particular physics interest, are illustrated

Fusion Energy Division progress report, January 1, 1992--December 31, 1994

Energy Technology Data Exchange (ETDEWEB)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.; Shannon, T.E.

1995-09-01

The report covers all elements of the ORNL Fusion Program, including those implemented outside the division. Non-fusion work within FED, much of which is based on the application of fusion technologies and techniques, is also discussed. The ORNL Fusion Program includes research and development in most areas of magnetic fusion research. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US and international fusion efforts. The research discussed in this report includes: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices; development and testing of plasma diagnostic tools and techniques; assembly and distribution of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; and development and testing of materials for fusion devices. The activities involving the use of fusion technologies and expertise for non-fusion applications ranged from semiconductor manufacturing to environmental management.

Fusion Energy Division progress report, January 1, 1992--December 31, 1994

International Nuclear Information System (INIS)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.; Shannon, T.E.

1995-09-01

The report covers all elements of the ORNL Fusion Program, including those implemented outside the division. Non-fusion work within FED, much of which is based on the application of fusion technologies and techniques, is also discussed. The ORNL Fusion Program includes research and development in most areas of magnetic fusion research. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US and international fusion efforts. The research discussed in this report includes: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices; development and testing of plasma diagnostic tools and techniques; assembly and distribution of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; and development and testing of materials for fusion devices. The activities involving the use of fusion technologies and expertise for non-fusion applications ranged from semiconductor manufacturing to environmental management

Fusion Safety Program annual report, fiscal year 1994

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

1995-03-01

This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities

The Canadian Fusion Fuels Technology Project

International Nuclear Information System (INIS)

Dautovich, D.P.; Gierszewski, P.J.; Wong, K.Y.; Stasko, R.R.; Burnham, C.D.

1987-04-01

The Canadian Fusion Fuels Technology Project (CFFTP) is a national project whose aim is to develop capability in tritium and robotics technologies for application to international fusion development programs. Activities over the first five years have brought substantial interaction with the world's leading projects such as Tokamak Fusion Test Reactor (TFTR), the Joint European Torus (JET), and the Next European Torus (NET), Canadian R and D and engineering services, and hardware are in demand as these major projects prepare for tritium operation leading to the demonstration of energy breakeven around 1990. Global planning is underway for the next generation ignition experiment. It is anticipated this will provide increased opportunity for CFFTP and its contractors among industry, universities and governmental laboratories

Fusion Plasma Physics and ITER - An Introduction (1/4)

CERN Multimedia

CERN. Geneva

2011-01-01

In November 2006, ministers representing the world’s major fusion research communities signed the agreement formally establishing the international project ITER. Sited at Cadarache in France, the project involves China, the European Union (including Switzerland), India, Japan, the Russian Federation, South Korea and the United States. ITER is a critical step in the development of fusion energy: its role is to confirm the feasibility of exploiting magnetic confinement fusion for the production of energy for peaceful purposes by providing an integrated demonstration of the physics and technology required for a fusion power plant. The ITER tokamak is designed to study the “burning plasma” regime in deuterium-tritium (D-T) plasmas by achieving a fusion amplification factor, Q (the ratio of fusion output power to plasma heating input power), of 10 for several hundreds of seconds with a nominal fusion power output of 500MW. It is also intended to allow the study of steady-state plasma operation at Q≥5 by me...

IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

International Nuclear Information System (INIS)

Rennich, M.J.

1996-12-01

This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities

Preliminary results of the International Fusion Materials Irradiation Facility deuteron injector

Energy Technology Data Exchange (ETDEWEB)

Gobin, R.; Adroit, G.; Bogard, D.; Bourdelle, G.; Chauvin, N.; Delferriere, O.; Gauthier, Y.; Girardot, P.; Guiho, P.; Harrault, F.; Jannin, J. L.; Loiseau, D.; Mattei, P.; Roger, A.; Sauce, Y.; Senee, F.; Vacher, T. [Commissariat a l' Energie Atomique et aux Energie Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France)

2012-02-15

In the framework of the IFMIF-EVEDA project (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities), CEA/IRFU is in charge of the design, construction, and characterization of the 140 mA continuous deuteron injector, including the source and the low energy beam line. The electron cyclotron resonance ion source which operates at 2.45 GHz is associated with a 4-electrode extraction system in order to minimize beam divergence at the source exit. Krypton gas injection is foreseen in the 2-solenoid low energy beam line. Such Kr injection will allow reaching a high level of space charge compensation in order to improve the beam matching at the radio frequency quadrupole (RFQ) entrance. The injector construction is now completed on the Saclay site and the first plasma and beam production has been produced in May 2011. This installation will be tested with proton and deuteron beams either in pulsed or continuous mode at Saclay before shipping to Japan. In this paper, after a brief description of the installation, the preliminary results obtained with hydrogen gas injection into the plasma chamber will be reported.

Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

Wiffen, F. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Melton, Stephanie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-12-01

The realization of fusion energy is a formidable challenge with significant achievements resulting from close integration of the plasma physics and applied technology disciplines. Presently, the most significant technological challenge for the near-term experiments such as ITER, and next generation fusion power systems, is the inability of current materials and components to withstand the harsh fusion nuclear environment. The overarching goal of the Oak Ridge National Laboratory (ORNL) fusion materials program is to provide the applied materials science support and understanding to underpin the ongoing Department of Energy (DOE) Office of Science fusion energy program while developing materials for fusion power systems. In doing so the program continues to be integrated both with the larger United States (US) and international fusion materials communities, and with the international fusion design and technology communities.This document provides a summary of Fiscal Year (FY) 2015 activities supporting the Office of Science, Office of Fusion Energy Sciences Materials Research for Magnetic Fusion Energy (AT-60-20-10-0) carried out by ORNL. The organization of this report is mainly by material type, with sections on specific technical activities. Four projects selected in the Funding Opportunity Announcement (FOA) solicitation of late 2011 and funded in FY2012-FY2014 are identified by “FOA” in the titles. This report includes the final funded work of these projects, although ORNL plans to continue some of this work within the base program.

International bulletin on atomic and molecular data for fusion. No.6

International Nuclear Information System (INIS)

Katsonis, K.; Smith, F.J.

1978-10-01

This bulletin deals with atomic and molecular data for fusion (spectroscopic data, atomic and molecular collisions, surface effects, ...). Particular emphasis is given to data applicable to Tokamak devices. A bibliography for the most recent data presented in the document is provided. A description of work in progress and ''Data Requests'' in the fusion field are also mentioned. Cross-sections for the electron impact excitation of 2sub(p1/2) and 2sub(p3/2) states of the lithium-line ions C 3+ , F 23+ , Mo 39+ and W 71+ calculated in the relativistic Coulomb-Born approximation are presented

International bulletin on atomic and molecular data for fusion. No.2

International Nuclear Information System (INIS)

Beaty, E.C.; Katsonis, K.

1977-10-01

This bulletin deals with atomic and molecular data for fusion (spectroscopic data, atomic and molecular collisions, surface effects, ...). Particular emphasis is given to data applicable to Tokamak devices. A bibliography for the most recent data presented in the document is provided. A description of work in progress and ''Data Requests'' in the fusion field are also mentioned. Numerical data on light ion sputtering yields of first wall materials, electron capture and impact ionization for iron ions colliding with molecular hydrogen and charge exchange between multicharged ions and helium, argon, and, atomic or molecular hydrogen are given

A small molecule fusion inhibitor of dengue virus.

Science.gov (United States)

Poh, Mee Kian; Yip, Andy; Zhang, Summer; Priestle, John P; Ma, Ngai Ling; Smit, Jolanda M; Wilschut, Jan; Shi, Pei-Yong; Wenk, Markus R; Schul, Wouter

2009-12-01

The dengue virus envelope protein plays an essential role in viral entry by mediating fusion between the viral and host membranes. The crystal structure of the envelope protein shows a pocket (located at a "hinge" between Domains I and II) that can be occupied by ligand n-octyl-beta-D-glucoside (betaOG). Compounds blocking the betaOG pocket are thought to interfere with conformational changes in the envelope protein that are essential for fusion. Two fusion assays were developed to examine the anti-fusion activities of compounds. The first assay measures the cellular internalization of propidium iodide upon membrane fusion. The second assay measures the protease activity of trypsin upon fusion between dengue virions and trypsin-containing liposomes. We performed an in silico virtual screening for small molecules that can potentially bind to the betaOG pocket and tested these candidate molecules in the two fusion assays. We identified one compound that inhibits dengue fusion in both assays with an IC(50) of 6.8 microM and reduces viral titers with an EC(50) of 9.8 microM. Time-of-addition experiments showed that the compound was only active when present during viral infection but not when added 1h later, in agreement with a mechanism of action through fusion inhibition.

(Fusion energy research)

Energy Technology Data Exchange (ETDEWEB)

Phillips, C.A. (ed.)

1988-01-01

This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer.

[Fusion energy research

International Nuclear Information System (INIS)

Phillips, C.A.

1988-01-01

This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer

Pacing the US magnetic fusion program

International Nuclear Information System (INIS)

1989-01-01

This study addresses the priority and pace of the nation's magnetic fusion research and development program in the context of long-term national energy policy. In particular, the committee interpreted its task as follows: To review the implications of long-term national energy policy for current research and development in magnetic fusion; to identify factors that should enter the further development of such policy to reduce risks associated with the future electricity supply system; to propose criteria applicable to research and develop in electric generation in reaching long-term energy policy goals; to apply these criteria to magnetic fusion and alternative electric generation technologies in order to develop recommendations on the priority pace of the magnetic fusion program; and to present its results in a final report. The most important goals of the US Department of Energy's current Magnetic Fusion Energy Program Plan are to demonstrate the scientific and engineering feasibility of fusion, Demonstrating engineering feasibility will require the design, construction, and operation of an engineering test reactor, which the plan envisions financing through a combination of domestic and international funding. The committee believes that current domestic program funding levels are inadequate to meet even the near-term objectives of the plan

History and status of magnetic fusion research; Evolution et statut des recherches sur la fusion controlee

Energy Technology Data Exchange (ETDEWEB)

Jacquinot, J. [CEA Saclay, Cabinet du Haut Commissaire, 91 - Gif-sur-Yvette (France)

2008-02-15

Ever since the understanding of the basic process which powers the stars has been elucidated, humanity has been dreaming to master controlled fusion for peaceful purposes. Controlled fusion in a steady state regime must use magnetic confinement of a gas (plasma) heated up to 150 millions degrees. Physics and technology involved in such a state are extremely complex and went through many up and down phases. Nevertheless, the overall progress has been spectacular and a significant amount of energy could be produced in a well controlled manner. On this basis, an international organisation of unprecedented magnitude involving 34 countries has started working in Cadarache for the construction of the ITER project. It aims at the scientific demonstration of controlled fusion at the level of 500 MW and a power gain of 10. (author)

Fifty years in fusion and the way forward

International Nuclear Information System (INIS)

Jacquinot, J.

2010-01-01

This particular 'Fusion Pioneers Memorial lecture' was given 50 years after the first historical FEC conference in 1958. It was a unique occasion to perform a global reflection on thermonuclear fusion which is summarized in this paper. We first consider the case for fusion energy then move on to the scientific achievements during the past five decades. Finally, the lessons drawn from the past give a framework to consider the challenges ahead of us. The 1958 pioneers had the vision of the vital importance of international collaboration to succeed in this unique endeavour. Fifty years later, this vision has amply proven its worth. Looking at the way forward, this vision constitutes a strong basis to harness fusion energy in the decades to come.

Research Needs for Magnetic Fusion Energy Sciences

Energy Technology Data Exchange (ETDEWEB)

Neilson, Hutch

2009-07-01

Nuclear fusion — the process that powers the sun — offers an environmentally benign, intrinsically safe energy source with an abundant supply of low-cost fuel. It is the focus of an international research program, including the ITER fusion collaboration, which involves seven parties representing half the world’s population. The realization of fusion power would change the economics and ecology of energy production as profoundly as petroleum exploitation did two centuries ago. The 21st century finds fusion research in a transformed landscape. The worldwide fusion community broadly agrees that the science has advanced to the point where an aggressive action plan, aimed at the remaining barriers to practical fusion energy, is warranted. At the same time, and largely because of its scientific advance, the program faces new challenges; above all it is challenged to demonstrate the timeliness of its promised benefits. In response to this changed landscape, the Office of Fusion Energy Sciences (OFES) in the US Department of Energy commissioned a number of community-based studies of the key scientific and technical foci of magnetic fusion research. The Research Needs Workshop (ReNeW) for Magnetic Fusion Energy Sciences is a capstone to these studies. In the context of magnetic fusion energy, ReNeW surveyed the issues identified in previous studies, and used them as a starting point to define and characterize the research activities that the advance of fusion as a practical energy source will require. Thus, ReNeW’s task was to identify (1) the scientific and technological research frontiers of the fusion program, and, especially, (2) a set of activities that will most effectively advance those frontiers. (Note that ReNeW was not charged with developing a strategic plan or timeline for the implementation of fusion power.)

1981 Annual Status Report: thermonuclear fusion technology

International Nuclear Information System (INIS)

1982-01-01

The work perfomed on 1981 concerns four projects, namely: - The project 1: ''Reactor Studies''. During 1981 this activity was made in support to the European participation to the INTOR (INternational TOkamak Reactor) studies. This represents a collaborative effort among Europe, Japan; USA and USSR, under the auspices of IAEA, to design a major fusion experiment beyond the upcoming generation of large tokamaks. - The Project 2: ''Blanket Technology'' has the aim to investigate the behaviour of blanket materials in fusion conditions. - The Project 3: ''Materials Sorting and Development'' has the aim to assess the mechanical properties and radiation damage of standard and advanced materials suited for structures, in particular for application as first wall of the fusion reactors. - The Project 4: ''Cyclotron Operation and Experiments'' has the task to exploit a cyclotron to simulate radiation damages to materials in a fusion ambient

Clean steels for fusion

International Nuclear Information System (INIS)

Gelles, D.S.

1995-03-01

Fusion energy production has an inherent advantage over fission: a fuel supply with reduced long term radioactivity. One of the leading candidate materials for structural applications in a fusion reactor is a tungsten stabilized 9% chromium Martensitic steel. This alloy class is being considered because it offers the opportunity to maintain that advantage in the reactor structure as well as provide good high temperature strength and radiation induced swelling and embrittlement resistance. However, calculations indicate that to obtain acceptable radioactivity levels within 500 years after service, clean steel will be required because the niobium impurity levels must be kept below about 2 appm and nickel, molybdenum, nitrogen, copper, and aluminum must be intentionally restricted. International efforts are addressing the problems of clean steel production. Recently, a 5,000 kg heat was vacuum induction melted in Japan using high purity commercial raw materials giving niobium levels less than 0.7 appm. This paper reviews the need for reduced long term radioactivity, defines the advantageous properties of the tungsten stabilized Martensitic steel class, and describes the international efforts to produce acceptable clean steels

Comprehensive safety analysis code system for nuclear fusion reactors II: Thermal analysis during plasma disruptions for international thermonuclear experimental reactor

International Nuclear Information System (INIS)

Honda, T.; Maki, K.; Okazaki, T.

1994-01-01

Thermal characteristics of a fusion reactor [International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activity] during plasma disruptions have been analyzed by using a comprehensive safety analysis code for nuclear fusion reactors. The erosion depth due to disruptions for the armor of the first wall depends on the current quench time of disruptions occurring in normal operation. If it is possible to extend the time up to ∼50 ms, the erosion depth is considerably reduced. On the other hand, the erosion depth of the divertor is ∼570 μm for only one disruption, which is determined only by the thermal flux during the thermal quench. This means that the divertor plate should be exchanged after about nine disruptions. Counter-measures are necessary for the divertor to relieve disruption influences. As other scenarios of disruptions, beta-limit disruptions and vertical displacement events were also investigated quantitatively. 13 refs., 5 figs

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

Energy Technology Data Exchange (ETDEWEB)

Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

2000-08-01

In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

International Nuclear Information System (INIS)

2000-02-01

This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

Insulators for fusion applications

International Nuclear Information System (INIS)

1987-04-01

Design studies for fusion devices and reactors have become more detailed in recent years and with this has come a better understanding of requirements and operating conditions for insulators in these machines. Ceramic and organic insulators are widely used for many components of fusion devices and reactors namely: radio frequency (RF) energy injection systems (BeO, Al 2 O 3 , Mg Al 2 O 4 , Si 3 N 4 ); electrical insulation for the torus structure (SiC, Al 2 O 3 , MgO, Mg Al 2 O 4 , Si 4 Al 2 O 2 N 6 , Si 3 N 4 , Y 2 O 3 ); lightly-shielded magnetic coils (MgO, MgAl 2 O 4 ); the toroidal field coil (epoxies, polyimides), neutron shield (B 4 C, TiH 2 ); high efficiency electrical generation; as well as the generation of very high temperatures for high efficiency hydrogen production processes (ZrO 2 and Al 2 O 3 - mat, graphite and carbon - felt). Timely development of insulators for fusion applications is clearly necessary. Those materials to be used in fusion machines should show high resistance to radiation damage and maintain their structural integrity. Now the need is urgent for a variety of radiation resistant materials, but much effort in these areas is required for insulators to be considered seriously by the design community. This document contains 14 papers from an IAEA meeting. It was the objective of this meeting to identify existing problems in analysing various situations of applications and requirements of electrical insulators and ceramics in fusion and to recommend strategies and different stages of implementation. This meeting was endorsed by the International Fusion Research Council

Investigation of high flux test module for the international fusion materials irradiation facilities (IFMIF)

International Nuclear Information System (INIS)

Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

2007-03-01

This report describes investigation on structure of a high neutron flux test module (HFTM) for the International Fusion Materials Irradiation Facilities (IFMIF). The HFTM is aimed for neutron irradiation of a specimen in a high neutron flux domain of the test cell for irradiation ground of IFMIF. We investigated the overall structure of the HFTM that was able to include specimens in a rig and thermocouple arrangement, an interface of control signal and support structure. Moreover, pressure and the amount of the bend in the module vessel (a rectangular section pressure vessel) were calculated. The module vessel did a rectangular section from limitation of a high neutron flux domain. Also, we investigated damage of thermocouples under neutron irradiation, which was a temperature sensor of irradiation materials temperature control demanded high precision. Based on these results, drawings on the HTFM structure. (author)

Fusion looks to the future - again

International Nuclear Information System (INIS)

Waldrop, M.M.

1984-01-01

The $46 million budget cut in the US magnetic fusion program introduced a new approach that abandons the race to build a working power reactor in favor of a long-term emphasis on science, technology, and international cooperation. Administration policies which favor private funding for demonstration projects and general concern over the deficit have changed the overall fusion policy, although there is some concern among research groups that the program will become unfocused without its detailed timetable. If this happens, they see the program becoming even more vulnerable to future budget cuts. 2 references

1982 annual status report: thermonuclear fusion technology

International Nuclear Information System (INIS)

1982-01-01

The objective of this programme is to study the technological problems related to ''Post Jet'' experimental machines and, in a longer range, to assess the engineering aspects of Fusion Power Reactor Plants. According to the decision taken by the Council of Ministers on the JRC multiannual programme (1980-1983), the work performed on 1982 concerns four projects, namely: The Project 1: ''Fusion Reactor Studies''concerns mainly the NET (Next European Torus) studies which have been continued in the framework of the European participation to INTOR (INternational TOkamak Reactor). This represents a collaborative effort to design a major fusion experiment beyond the-upcoming generation of large tokamaks. The Project 2: ''Blanket Technology'' has the aim to investigate the behaviour of blanket materials in fusion conditions. The Project 3: ''Materials Sorting and Development'' has the aim to assess the mechanical properties and radiation damage of standard and advanced materials suited for structures, in particular for application as first wall of the fusion reactors. The Project 4: ''Cyclotron Operation and Experiments''has the task to exploit a cyclotron to simulate radiation damages to materials in a fusion ambient

Fusion Canada issue 24

International Nuclear Information System (INIS)

1994-04-01

A short bulletin from the National Fusion Program highlighting in this issue the opening of the Garching ITER site, a CCFM/TdeV update,a tritium release field test, measuring radial profile of plasma current density on TdeV, power supplies for TdeV, 5th International Tritium Technology conference, and 1994 basic tritium course. 4 figs

Coordinated activities on evaluation of collisional data for fusion applications

International Nuclear Information System (INIS)

Chung, H.-K.; Braams, B. J.

2013-01-01

It is the role of the Atomic and Molecular Data Unit of the International Atomic Energy Agency to review progress in the production, compilation and evaluation of atomic, molecular and plasma-surface interaction (AM/PSI) data for the fusion program and to support the development of internationally recommended libraries of AM/PSI data for fusion. In response to increasing requests from the fusion community the Unit has increased its effort to promote the assessment of data quality by organizing a series of meetings on the relevant issues: 1) Error propagation and sensitivity analysis, 2) Current status of evaluated databases, 3) Uncertainty estimates of theoretical data, 4) Experimental data evaluation, 5) Data evaluation methods and semi-empirical fits and 6) Establishment of an evaluators’ network. The discussions and conclusions are summarized here

Plasma physics for controlled fusion

CERN Document Server

Miyamoto, Kenro

2016-01-01

This new edition presents the essential theoretical and analytical methods needed to understand the recent fusion research of tokamak and alternate approaches. The author describes magnetohydrodynamic and kinetic theories of cold and hot plasmas in detail. The book covers new important topics for fusion studies such as plasma transport by drift turbulence, which depend on the magnetic configuration and zonal flows. These are universal phenomena of microturbulence. They can modify the onset criterion for turbulent transport, instabilities driven by energetic particles as well as alpha particle generation and typical plasma models for computer simulation. The fusion research of tokamaks with various new versions of H modes are explained. The design concept of ITER, the international tokamak experimental reactor, is described for inductively driven operations as well as steady-state operations using non-inductive drives. Alternative approaches of reversed-field pinch and its relaxation process, stellator includi...

Helium cooling of fusion reactors

International Nuclear Information System (INIS)

Wong, C.P.C.; Baxi, C.; Bourque, R.; Dahms, C.; Inamati, S.; Ryder, R.; Sager, G.; Schleicher, R.

1994-01-01

On the basis of worldwide design experience and in coordination with the evolution of the International Thermonuclear Experimental Reactor (ITER) program, the application of helium as a coolant for fusion appears to be at the verge of a transition from conceptual design to engineering development. This paper presents a review of the use of helium as the coolant for fusion reactor blanket and divertor designs. The concept of a high-pressure helium cooling radial plate design was studied for both ITER and PULSAR. These designs can resolve many engineering issues, and can help with reaching the goals of low activation and high performance designs. The combination of helium cooling, advanced low-activation materials, and gas turbine technology may permit high thermal efficiency and reduced costs, resulting in the environmental advantages and competitive economics required to make fusion a 21st century power source. ((orig.))

Nuclear fusion research in Australia

International Nuclear Information System (INIS)

Cheetham, A.D.

1997-01-01

In this paper the recently formed National Plasma Fusion Research Facility centred around the H-1NF Heliac, located at the Australian National University, the Institute of Advanced Studies is described in the context of the international Stellarator program and the national collaboration with the Australian Fusion Research Group. The objectives of the facility and the planned physics research program over the next five years are discussed and some recent results will be presented. The facility will support investigations in the following research areas: finite pressure equilibrium and stability, transport in high temperature plasmas, plasma heating and formation, instabilities and turbulence, edge plasma physics and advanced diagnostic development

Fusion plasma physics during half a century

International Nuclear Information System (INIS)

Lehnert, Bo

1999-08-01

A review is given on the potentialities of fusion energy with respect to energy production and related environmental problems, the various approaches to controlled thermonuclear fusion, the main problem areas of research, the historical development, the present state of investigations, and future perspectives. This article also presents a personal memorandum of the author. Thereby special reference will be given to part of the research conducted at the Royal Institute of Technology in Stockholm, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades. In large tokamak experiments temperatures above the ignition limit of about 10 8 K have been reached under break-even conditions where the fusion power generation is comparable to the energy loss. A power producing fusion reactor could in principle be realized already today, but it would not become technically and economically efficient. The future international research programme has therefore to be conducted along broad lines, with necessary ingredients of basis research and new ideas, and also within lines of magnetic confinement being alternative to that of tokamaks

Blue energy - The story of thermonuclear fusion energy

International Nuclear Information System (INIS)

Laval, G.

2007-01-01

The author has written a story of thermonuclear fusion as a future source of energy. This story began about 50 years ago and its last milestone has been the decision of building the ITER machine. This decision has been taken by an international collaboration including a large part of the humanity which shows how great are the expectations put on fusion and that fusion deserves confidence now. For long years fusion energy has been the subject of large controversy due to the questioning about the overcoming of huge theoretical and technological difficulties. Different machines have been built to assess new theoretical developments and to prepare the next step. The physics of hot plasmas has been understood little by little at the pace of the discovery of new instabilities taking place in fusion plasmas. The 2 unique today options: the tokamak-type machine and the laser-driven inertial confinement machine took the lead relatively quickly. (A.C.)

ITER session at the IAEA fusion energy conference

International Nuclear Information System (INIS)

Stewart, M.J.

2003-01-01

A highlight of this year's Fusion Energy Conference, held in Lyon, France, on 14-19 October, was the participation by the ITER Parties in both a Special ITER Informal Session and in the Fusion Institute Exhibition at the Paella's des Congres de Lyon. These gave conference participants an opportunity to hear the latest on this collaborative international fusion energy research and development project, and to speak with the experts from each of the four sites being offered for the construction of ITER. The Special ITER Informal Session was held on the evening of 16 October and it was very well attended, with approximately 350 conference participants attending

Fusion research and technology records in INIS database

International Nuclear Information System (INIS)

Hillebrand, C.D.

1998-01-01

This article is a summary of a survey study ''''A survey on publications in Fusion Research and Technology. Science and Technology Indicators in Fusion R and T'''' by the same author on Fusion R and T records in the International Nuclear Information System (INIS) bibliographic database. In that study, for the first time, all scientometric and bibliometric information contained in a bibliographic database, using INIS records, is analyzed and quantified, specific to a selected field of science and technology. A variety of new science and technology indicators which can be used for evaluating research and development activities is also presented in that study that study

Safety of magnetic fusion facilities: Volume 2, Guidance

International Nuclear Information System (INIS)

1995-01-01

This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

Canadian capabilities in fusion fuels technology and remote handling

International Nuclear Information System (INIS)

1987-10-01

This report describes Canadian expertise in fusion fuels technology and remote handling. The Canadian Fusion Fuels Technology Project (CFFTP) was established and is funded by the Canadian government, the province of Ontario and Ontario Hydro to focus on the technology necessary to produce and manage the tritium and deuterium fuels to be used in fusion power reactors. Its activities are divided amongst three responsibility areas, namely, the development of blanket, first wall, reactor exhaust and fuel processing systems, the development of safe and reliable operating procedures for fusion facilities, and, finally, the application of these developments to specific projects such as tritium laboratories. CFFTP also hopes to utilize and adapt Canadian developments in an international sense, by, for instance, offering training courses to the international tritium community. Tritium management expertise is widely available in Canada because tritium is a byproduct of the routine operation of CANDU reactors. Expertise in remote handling is another byproduct of research and development of of CANDU facilities. In addition to describing the remote handling technology developed in Canada, this report contains a brief description of the Canadian tritium laboratories, storage beds and extraction plants as well as a discussion of tritium monitors and equipment developed in support of the CANDU reactor and fusion programs. Appendix A lists Canadian manufacturers of tritium equipment and Appendix B describes some of the projects performed by CFFTP for offshore clients

Second international comparison on measuring techniques of tritium production rate for fusion neutronics experiments (ICMT-2)

International Nuclear Information System (INIS)

Maekawa, Fujio; Maekawa, Hiroshi

1993-02-01

An second international comparison on measuring techniques of tritium production rates for fusion neutronics experiments (ICMT-2) has been performed. The purpose is to evaluate the measurement accuracy of tritium production rates in the current measurement techniques. Two 14 MeV neutron source facilities, FNS at JAERI-Japan and LOTUS at EPFL-Switzerland, were used for this purpose. Nine groups out of seven countries participated in this program. A fusion simulated blanket assembly of simple-geometry was served as the test bed at each facility, in which Li-containing samples from the participants were irradiated in an uniform neutron field. The tritium production rates were determined by the participants using their own ways by using the liquid scintillation counting method. Tritiated water sample with unknown but the same concentration was also distributed and its concentration was measured to make a common reference. The standard deviation of measured tritium production rates among participants was about 10 % for both FNS and LOTUS irradiation levels: 4x10 -13 T-atoms/Li-atom and 1.6x10 -12 T-atoms/Li-atom at a sample, respectively. This standard deviation exceeds the expected deviation of 5 % in this program. It is presumed that the deviation of 10 % is caused mainly by the systematic and unknown errors in a process of tritium extraction from the irradiated samples depending on each organization. (author)

Fusion-related work at the Nuclear Energy Agency Data Bank

International Nuclear Information System (INIS)

Henriksson, H.; Mompean, F.J.; Kodeli, I.

2007-01-01

The OECD Nuclear Energy Agency (NEA) Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear reaction data. Through its activities in the reaction data field, the NEA participates in the preparation of data for the modelling of future nuclear facility concepts and the development of reactor installations. A working party at the NEA on international nuclear data evaluation cooperation (WPEC) is established to promote the exchange of nuclear data evaluations, measurements, nuclear model calculations and validation. WPEC provides a framework for co-operative activities, such as the high priority request list for experimental data of special interest for certain applications, such as IFMIF or ITER. The NEA Data Bank administrates the collection and validation as well as the distribution of the Joint Evaluated Fusion and Fission (JEFF) library, where the activities in the European Fusion and Activation File projects (EFF and EAF respectively) play an important role for new data evaluations. The topics cover verification of activation and transport data, calculation methods and validation via integral experiments. The EFF project brings together all available expertise in Europe related to the nuclear data requirements of existing and future fusion devices, and the project contributed greatly to the internationally recognised nuclear data library JEFF-3.1, released in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the Shielding Integral Benchmark Archive Database (SINBAD) database. SINBAD is an internationally established set of radiation shielding and dosimetry data containing over 80 experiments relevant for reactor and accelerator shielding. About 30 of these experiments are dedicated to fusion blanket neutronics. Materials

Fusion Plasma Theory project summaries

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively-participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at US government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the US Fusion Energy Program.

Fusion plasma theory project summaries

Science.gov (United States)

1993-10-01

This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at U.S. government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the U.S. Fusion Energy Program.

Fusion Plasma Theory project summaries

International Nuclear Information System (INIS)

1993-10-01

This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively-participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at US government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the US Fusion Energy Program

Plasma-Jet Magneto-Inertial Fusion Burn Calculations

Science.gov (United States)

Santarius, John

2010-11-01

Several issues exist related to using plasma jets to implode a Magneto-Inertial Fusion (MIF) liner onto a magnetized plasmoid and compress it to fusion-relevant temperatures [1]. The poster will explore how well the liner's inertia provides transient plasma confinement and affects the burn dynamics. The investigation uses the University of Wisconsin's 1-D Lagrangian radiation-hydrodynamics code, BUCKY, which solves single-fluid equations of motion with ion-electron interactions, PdV work, table-lookup equations of state, fast-ion energy deposition, pressure contributions from all species, and one or two temperatures. Extensions to the code include magnetic field evolution as the plasmoid compresses plus dependence of the thermal conductivity on the magnetic field. [4pt] [1] Y.C. F. Thio, et al.,``Magnetized Target Fusion in a Spheroidal Geometry with Standoff Drivers,'' in Current Trends in International Fusion Research, E. Panarella, ed. (National Research Council of Canada, Ottawa, Canada, 1999), p. 113.

IFMIF suitability for evaluation of fusion functional materials

International Nuclear Information System (INIS)

Casal, N.; Sordo, F.; Mota, F.; Jordanova, J.; Garcia, A.; Ibarra, A.; Vila, R.; Rapisarda, D.; Queral, V.; Perlado, M.

2011-01-01

The International Fusion Materials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusion materials at relevant fusion irradiation conditions. During the design of IFMIF special attention was paid to the structural materials for the blanket and first wall, because they will be exposed to the most severe irradiation conditions in a fusion reactor. Also the irradiation of candidate materials for solid breeder blankets is planned in the IFMIF reference design. This paper focuses on the assessment of the suitability of IFMIF irradiation conditions for testing functional materials to be used in liquid blankets and diagnostics systems, since they are been also considered within IFMIF objectives. The study has been based on the analysis and comparison of the main expected irradiation parameters in IFMIF and DEMO reactor.

[International Thermonuclear Experimental Reactor support

International Nuclear Information System (INIS)

Dean, S.O.

1990-01-01

This report summarizes the activities under LLNL Purchase Order B089367, the purpose of which is to ''support the University/Lawrence Livermore National Laboratory Magnetic Fusion Program by evaluating the status of research relative to other national and international programs and assist in long-range plans and development strategies for magnetic fusion in general and for ITER in particular.'' Two specific subtasks are included: ''to review the LLNL Magnet Technology Development Program in the context of the International Thermonuclear Experimental Reactor Design Study'' and to ''assist LLNL to organize and prepare materials for an International Thermonuclear Experimental Reactor Design Study information meeting.''

Summary on inertial confinement fusion

International Nuclear Information System (INIS)

Meyer-Ter-Vehn, J.

1995-01-01

Highlights on inertial confinement during the fifteenth international conference on plasma physics and controlled nuclear fusion are briefly summarized. Specifically the following topics are discussed: the US National Ignition Facility presently planned by the US Department of Energy; demonstration of diagnostics for hot spot formation; declassification of Hohlraum target design; fusion targets, in particular, the Hohlraum target design for the National Ignition Facility (NIF), Hohlraum experiments, direct drive implosions, ablative Rayleigh-Taylor instabilities, laser imprinting (of perturbations by the laser on the laser target surface), hot spot formation and mixing, hot spot implosion experiments at Lawrence Livermore National Laboratory, Livermore, USA, time resolving hot spot dynamics at the Institute of Laser Engineering (ILE), Osaka, Japan, laser-plasma interaction

Code of a Tokamak Fusion Energy Facility ITER

International Nuclear Information System (INIS)

Yasuhide Asada; Kenzo Miya; Kazuhiko Hada; Eisuke Tada

2002-01-01

The technical structural code for ITER (International Thermonuclear Experimental Fusion Reactor) and, as more generic applications, for D-T burning fusion power facilities (hereafter, Fusion Code) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Introduction of such newly developed technologies as inspection-free automatic welding into the Fusion Code is rationalized by a pilot application of a new code concept of s ystem-based code for integrity . The code concept means an integration of element technical items necessary for construction, operation and maintenance of mechanical components of fusion power facilities into a single system to attain an optimization of the total margin of these components. Unique and innovative items of the Fusion Code are typically as follows: - Use of non-metals; - Cryogenic application; - New design margins on allowable stresses, and other new design rules; - Use of inspection-free automatic welding, and other newly developed fabrication technologies; - Graded approach of quality assurance standard to cover radiological safety-system components as well as non-safety-system components; - Consideration on replacement components. (authors)

Overview of materials R and D for fusion and Gen-4

Energy Technology Data Exchange (ETDEWEB)

Kohyama, A. [Kyoto Univ., lnstitute of Advanced Energy (Japan); Tavassoli, F.; Carre, F.; Billot, P. [CEA Saclay, 91 - Gif sur Yvette (France); Zinide, S. [Oak Ridge National Laboratory, Materials Science and Technology Div., AK TN (United States)

2007-07-01

Full text of publication follows: In view of the growing need for energy, the risk of exhaustion of fossil fuel and the problem of global warming, the nuclear energy is receiving added attention as a realistic and viable advanced solution. International collaborations on Generation IV (Gen-IV) fission reactors and on ITER and DEMO fusion reactors are developing. This is particularly the case in the sector of materials, where they hold the key to success of these systems. The international community has recognized and planned its materials R and D work for Fusion and Gen-IV reactors with the following considerations: 1- The time allotted to materials R and D is short and may not allow development of totally new materials. 2- Activities required, to cover existing materials variations and service conditions necessary for reactor design, are very time consuming. 3- The work to be done must build upon the existing knowledge of materials and avoid duplications. Although ITER for fusion and Generation four International Forum (GIF) for Gen-IV are important international collaborative programs, they are insufficient to meet all the national energy policies of the participating countries. This paper provides an overview of the materials R and D carried out for fusion and Gen-IV reactors at international and national levels. Materials programs discussed include both cross-cutting and reactor specific actions, where major tasks can be defined as: + Cross-cutting materials tasks: - materials for high temperature service; - materials with neutron damage tolerance; - materials behavior analysis and modeling; - high temperature design methodology. + Reactor specific materials tasks: - very high temperature alloys; - carbon, high temperature ceramics and their composites; - materials compatibilities. Starting with a brief introduction of materials R and D strategies, ITER and Broader Approach (BA), overall activities for fusion and GIF for Gen-IV will be reviewed. Domestic

The International Thermonuclear Experimental Reactor (ITER) international organisation: which laws apply to this international nuclear operator?

International Nuclear Information System (INIS)

Grammatico-Vidal, L.

2009-01-01

ITER is being carried out by way of international collaboration between seven partners (the European atomic energy community -EURATOM-, China, India, Japan, Russia, south korea and the United states) which together represent more than half the world population. From a project organisation point of view, it is supported by both financial and in-kind contributions provided by each of the partner; each member makes its contribution through a special legal entity called a 'domestic agency' to an international organisation which was set up by the Agreement on the Establishment of an International Fusion Energy Organization for the joint Implementation of the ITER project signed in Paris on 21. november 2006 and which entered into force on 24. october 2007 after ratification by each of the partners. The international agreement is to remain in effect for a period of 35 years and may be renewed for a period of 10 years without any change to its content. It is supplemented by an agreement of the same date on the privileges and immunities of the organisation and of its staff. The function of the ITER organisation is to construct, commission, operate and permanently shutdown the ITER facility, to encourage their exploitation by laboratories, other institutions and personnel participating in the fusion energy research and development programmes of its members and to promote public understanding and acceptance of fusion energy. The unique institutional structure for this project will be described briefly in the introduction before analysing the law applicable to this international organisation, a French nuclear operator, unique in France today. (N.C.)

Development of a Portable Fusion Neutron Generator

Energy Technology Data Exchange (ETDEWEB)

Oh, Byung-Hoon; In, Sang-Ryul; Jin, Jeong-Tae; Chang, Dae-Sik; Jang, Doh-Yun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Cheol Ho [Hanyang Univ., Seoul (Korea, Republic of)

2015-05-15

For this purpose commercial ones, fast neutron yield from 10{sup 7} to 10{sup 11}, are supplied by several companies and research groups around the world. But internally the following limits make it difficult to develop the related application systems by domestic companies and/or research groups. - Limited life time - High price - Frequent trouble Not only to remove these limits but also to find out new internal application fields, it is necessary to develop our own domestic neutron generators. With the related technologies earned during fusion related researches, we did start to develop movable neutron generators from small one to big one, which could cover different fusion neutron yields. In this presentation the design and initial experimental results on the developed small neutron generator with a final target of 10{sup 8} n/s of 14 MeV neutrons, will be summarized.

Fusion: from sacred cow to white elephant?

International Nuclear Information System (INIS)

Wooldridge, J.

1994-01-01

Controlled thermonuclear fusion has the potential to supply lots of relatively cheap power relatively cheaply. It is also renewable and has public support. Because of this potential, fusion has been able to attract huge research funds. The four main research programmes, in Europe, USA, Japan and Russia, include cooperation on the International Thermonuclear Experimental Reactor, ITER. The siting of this reactor will be decided in 1998 and it is due to start operation in 2010. It should lead to a demonstration reactor, DEMO, after which a prototype commercial reactor is envisaged for 2030-2050. But this is too far away to solve some of the immediate energy problems such as carbon dioxide emissions and global warming. So even if the technical problems are solved, fusion may not be the wonder energy source when it finally arrives; the trend is away from centralised, high cost, high output generation. Fusion research has taken interest and money away from other alternatives such as tidal energy, fuel cells and photovoltaic cells. Photovoltaics in particular look more feasible than fusion and could be in place far sooner, but lack the funding for research. (UK)

Fusion plasma physics during half a century

Energy Technology Data Exchange (ETDEWEB)

Lehnert, Bo

1999-08-01

A review is given on the potentialities of fusion energy with respect to energy production and related environmental problems, the various approaches to controlled thermonuclear fusion, the main problem areas of research, the historical development, the present state of investigations, and future perspectives. This article also presents a personal memorandum of the author. Thereby special reference will be given to part of the research conducted at the Royal Institute of Technology in Stockholm, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades. In large tokamak experiments temperatures above the ignition limit of about 10{sup 8} K have been reached under break-even conditions where the fusion power generation is comparable to the energy loss. A power producing fusion reactor could in principle be realized already today, but it would not become technically and economically efficient. The future international research programme has therefore to be conducted along broad lines, with necessary ingredients of basis research and new ideas, and also within lines of magnetic confinement being alternative to that of tokamaks.

Fusion Energy Division annual progress report, period ending December 31, 1989

Energy Technology Data Exchange (ETDEWEB)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

1991-07-01

The Fusion Program of Oak Ridge National Laboratory (ORNL) carries out research in most areas of magnetic confinement fusion. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US fusion program and the international fusion community. Issued as the annual progress report of the ORNL Fusion Energy Division, this report also contains information from components of the Fusion Program that are carried out by other ORNL organizations (about 15% of the program effort). The areas addressed by the Fusion Program and discussed in this report include the following: Experimental and theoretical research on magnetic confinement concepts, engineering and physics of existing and planned devices, including remote handling, development and testing of diagnostic tools and techniques in support of experiments, assembly and distribution to the fusion community of databases on atomic physics and radiation effects, development and testing of technologies for heating and fueling fusion plasmas, development and testing of superconducting magnets for containing fusion plasmas, development and testing of materials for fusion devices, and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas. Highlights from program activities are included in this report.

Fusion Energy Division annual progress report, period ending December 31, 1989

International Nuclear Information System (INIS)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

1991-07-01

The Fusion Program of Oak Ridge National Laboratory (ORNL) carries out research in most areas of magnetic confinement fusion. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US fusion program and the international fusion community. Issued as the annual progress report of the ORNL Fusion Energy Division, this report also contains information from components of the Fusion Program that are carried out by other ORNL organizations (about 15% of the program effort). The areas addressed by the Fusion Program and discussed in this report include the following: Experimental and theoretical research on magnetic confinement concepts, engineering and physics of existing and planned devices, including remote handling, development and testing of diagnostic tools and techniques in support of experiments, assembly and distribution to the fusion community of databases on atomic physics and radiation effects, development and testing of technologies for heating and fueling fusion plasmas, development and testing of superconducting magnets for containing fusion plasmas, development and testing of materials for fusion devices, and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas. Highlights from program activities are included in this report

Recombinant fusion protein of albumin-retinol binding protein inactivates stellate cells

International Nuclear Information System (INIS)

Choi, Soyoung; Park, Sangeun; Kim, Suhyun; Lim, Chaeseung; Kim, Jungho; Cha, Dae Ryong; Oh, Junseo

2012-01-01

Highlights: ► We designed novel recombinant albumin-RBP fusion proteins. ► Expression of fusion proteins inactivates pancreatic stellate cells (PSCs). ► Fusion proteins are successfully internalized into and inactivate PSCs. ► RBP moiety mediates cell specific uptake of fusion protein. -- Abstract: Quiescent pancreatic- (PSCs) and hepatic- (HSCs) stellate cells store vitamin A (retinol) in lipid droplets via retinol binding protein (RBP) receptor and, when activated by profibrogenic stimuli, they transform into myofibroblast-like cells which play a key role in the fibrogenesis. Despite extensive investigations, there is, however, currently no appropriate therapy available for tissue fibrosis. We previously showed that the expression of albumin, composed of three homologous domains (I–III), inhibits stellate cell activation, which requires its high-affinity fatty acid-binding sites asymmetrically distributed in domain I and III. To attain stellate cell-specific uptake, albumin (domain I/III) was coupled to RBP; RBP-albumin domain III (R-III) and albumin domain I -RBP-albumin III (I-R-III). To assess the biological activity of fusion proteins, cultured PSCs were used. Like wild type albumin, expression of R-III or I-R-III in PSCs after passage 2 (activated PSCs) induced phenotypic reversal from activated to fat-storing cells. On the other hand, R-III and I-R-III, but not albumin, secreted from transfected 293 cells were successfully internalized into and inactivated PSCs. FPLC-purified R-III was found to be internalized into PSCs via caveolae-mediated endocytosis, and its efficient cellular uptake was also observed in HSCs and podocytes among several cell lines tested. Moreover, tissue distribution of intravenously injected R-III was closely similar to that of RBP. Therefore, our data suggest that albumin-RBP fusion protein comprises of stellate cell inactivation-inducing moiety and targeting moiety, which may lead to the development of effective anti

International bulletin on atomic and molecular data for fusion. No. 48

International Nuclear Information System (INIS)

1994-10-01

This bulletin provides atomic and molecular data references relevant to thermonuclear fusion research and technology. In part I the indexing of the papers is given separately for (i) structure and spectra (energy levels, wavelengths; transition probabilities, oscillator strengths; interatomic potentials), (ii) atomic and molecular collisions (photon collisions, electron collisions, heavy particle collisions), and (iii) surface interactions (sputtering, surface damage, blistering, flaking, arcing, chemical reactions). Part II contains the bibliographic data for the above listed topics and for plasma composition and impurities, plasma heating, cooling and fuelling, high energy laser- and beam- matter interaction, bibliographic and numerical data collections, and on interaction of atomic particles with fields. Also included are sections on atomic and molecular data needs for fusion research and on news about ALADDIN (A Labelled Atomic Data Interface) and evaluated-data bases

Japanese perspective of fusion nuclear technology from ITER to DEMO

International Nuclear Information System (INIS)

Tanaka, Satoru; Takatsu, Hideyuki

2007-01-01

The world fusion community is now launching construction of ITER, the first nuclear-grade fusion machine in the world. In parallel to the ITER program, Broader Approach (BA) activities are to be initiated in this year by EU and Japan, mainly at Rokkasho BA site in Japan, as complementary activities to ITER toward DEMO. The BA activities include IFMIFEVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) and DEMO design activities with generic technology R and Ds, both of which are critical to the rapid development of DEMO and commercial fusion power plants. The Atomic Energy Commission of Japan reviewed on-going third phase fusion program and issued the results of the review, 'On the policy of Nuclear Fusion Research and Development' in November 2005. In this report, it is anticipated that the ITER will be made operational in a decade and the programmatic objective can be met in the succeeding seven or eight years. Under this condition, the report presents a roadmap toward the DEMO and beyond and R and D items on fusion nuclear technology, indispensable for fusion energy utilization, are re-aligned. In the present paper, Japanese view and policy on ITER and beyond is summarized mainly from the viewpoints of nuclear fusion technology, and a minimum set of R and D elements on fusion nuclear technology, essential for fusion energy utilization, is presented. (orig.)

Fusion energy

International Nuclear Information System (INIS)

Gross, R.A.

1984-01-01

This textbook covers the physics and technology upon which future fusion power reactors will be based. It reviews the history of fusion, reaction physics, plasma physics, heating, and confinement. Descriptions of commercial plants and design concepts are included. Topics covered include: fusion reactions and fuel resources; reaction rates; ignition, and confinement; basic plasma directory; Tokamak confinement physics; fusion technology; STARFIRE: A commercial Tokamak fusion power plant. MARS: A tandem-mirror fusion power plant; and other fusion reactor concepts

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

1993-12-01

This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

Fusion Safety Program Annual Report, Fiscal Year 1996

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

1996-12-01

This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

International Bulletin on Atomic and Molecular Data for Fusion. No. 31

International Nuclear Information System (INIS)

Hughes, J.G.

1985-12-01

This bulletin presents a selected bibliography (363 literature pieces) on atomic and molecular data for fusion. It also gives a list of indexed papers on structure and spectra, atomic and molecular collisions, and surface interactions

Plasma physics and controlled fusion research during half a century

Energy Technology Data Exchange (ETDEWEB)

Lehnert, Bo

2001-06-01

A review is given on the historical development of research on plasma physics and controlled fusion. The potentialities are outlined for fusion of light atomic nuclei, with respect to the available energy resources and the environmental properties. Various approaches in the research on controlled fusion are further described, as well as the present state of investigation and future perspectives, being based on the use of a hot plasma in a fusion reactor. Special reference is given to the part of this work which has been conducted in Sweden, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades. Temperatures above the limit for ignition of self-sustained fusion reactions, i.e. at more than hundred million degrees, have been reached in large experiments and under conditions where the fusion power generation is comparable to the power losses. An energy producing fusion reactor could in principle be realized already today, but it would not become technically and economically efficient when being based on the present state of art. Future international research has therefore to be conducted along broad lines, with necessary ingredients of basic investigations and new ideas.

Plasma physics and controlled fusion research during half a century

International Nuclear Information System (INIS)

Lehnert, Bo

2001-06-01

A review is given on the historical development of research on plasma physics and controlled fusion. The potentialities are outlined for fusion of light atomic nuclei, with respect to the available energy resources and the environmental properties. Various approaches in the research on controlled fusion are further described, as well as the present state of investigation and future perspectives, being based on the use of a hot plasma in a fusion reactor. Special reference is given to the part of this work which has been conducted in Sweden, merely to identify its place within the general historical development. Considerable progress has been made in fusion research during the last decades. Temperatures above the limit for ignition of self-sustained fusion reactions, i.e. at more than hundred million degrees, have been reached in large experiments and under conditions where the fusion power generation is comparable to the power losses. An energy producing fusion reactor could in principle be realized already today, but it would not become technically and economically efficient when being based on the present state of art. Future international research has therefore to be conducted along broad lines, with necessary ingredients of basic investigations and new ideas

Osteoclast Fusion

DEFF Research Database (Denmark)

Marie Julie Møller, Anaïs; Delaissé, Jean-Marie; Søe, Kent

2017-01-01

on the nuclearity of fusion partners. While CD47 promotes cell fusions involving mono-nucleated pre-osteoclasts, syncytin-1 promotes fusion of two multi-nucleated osteoclasts, but also reduces the number of fusions between mono-nucleated pre-osteoclasts. Furthermore, CD47 seems to mediate fusion mostly through...... individual fusion events using time-lapse and antagonists of CD47 and syncytin-1. All time-lapse recordings have been studied by two independent observers. A total of 1808 fusion events were analyzed. The present study shows that CD47 and syncytin-1 have different roles in osteoclast fusion depending...... broad contact surfaces between the partners' cell membrane while syncytin-1 mediate fusion through phagocytic-cup like structure. J. Cell. Physiol. 9999: 1-8, 2016. © 2016 Wiley Periodicals, Inc....

First generation of fusion power plants: Design and technology. Proceedings of the 2. IAEA technical meeting

International Nuclear Information System (INIS)

2008-01-01

This series of meetings has been initiated under recommendation of the International Fusion Research Council for the IAEA and is expected to initiate, develop and mature ideas on fusion strategy that would be of benefit for all players. The present objectives of this meeting are to provide a forum to discuss concepts, technology and environmental aspects of future fusion power plants, the next step following ITER, their role in future energy mix and to assess a selection of urgent topics aiming at identifying the physics and the technological requirements that ITER and a fusion grade materials developing programme will have to address to support the construction of a DEMO(s) fusion power plant(s) prototype demonstrating viable economics. The meeting was organized in five sessions addressing five topics: - (PPCA) Power Plant Concepts and systems Analysis. - (MCP) Materials analysis/Components design/Plasma requirements - (NE) Non-Electric applications of fusion - (SESE) Social, Economic, Safety and Environmental aspects of fusion - (EP) Energy Policy, strategy and scenario for fusion development. A summary session took place at the end of the meeting. Thirty-three participants representing 12 Countries and 3 International Organizations were present at the meeting

Condensed matter nuclear science: Proceedings of the 11. international conference on cold fusion

International Nuclear Information System (INIS)

Biberian, Jean-Paul

2006-01-01

The tenth International Conference on Cold Fusion, ICCF 10, was held in Cambridge and then it appeared to the chairman Jean-Paul Biberian that the ideal choice for the venue of ICCF 11 would be Marseille. He considers that the field had matured and it was obvious that a scientific demonstration of Cold Fusion had been made. He realizes that a lot more is needed to be accomplished in the field of research and technology, but the answers to many of the questions of scientific community are available. It is known for sure that the phenomenon announced in 1989 by Martin Fleischmann and Stan Pons was real. Discoveries since their announcement, in particular the discovery that hydrogen, not only deuterium, may be nuclear active under certain conditions. It had been shown that the simple D + D producing helium reaction was not the only reaction channel. One had observed fission and transmutation beyond doubts, but there are probably more reactions than one currently knows. Several important new results were presented during the conference. The team headed by Irving Dardik confirmed that the super-waves they used in their electrolytic experiment help introducing more heat. Also Iwamura et al. showed new transmutation effects in their experiments of diffusion of deuterium gas through a complex structure of palladium and calcium oxide. A team of Russian scientists claimed that their experiments showed the existence of light monopoles. Czerski and Huke who were working in high-energy physics, discovered CMNS when they lowered the energy of the deuterium beam. They demonstrated that the cross section of the deuterium with deuterated metals was much higher than expected. They came to the conclusion that they were doing indeed cold fusion. Another important contribution was the one from the Vysotskii team from Ukraine, who confirmed their biological transmutation experiments. On the theory front there appears to be many problems. The initial idea of the necessity of high

Atomic and Plasma-Material Interaction Data for Fusion. V. 16

International Nuclear Information System (INIS)

Braams, B.J.; Chung, H.-K.

2014-03-01

A wide variety of atomic, molecular, radiative and plasma-wall interaction processes involving a mixture of atoms, ions and molecules occur in the plasmas produced in nuclear fusion experiments. In the low temperature divertor and near wall region, molecules and molecular ions are formed. The plasma particles react with electrons and with each other. Plasma modelling requires cross-sections and rate coefficients for all these processes, and in addition spectral signatures to support interpretation of data from fusion experiments. The mission of the International Atomic Energy Agency Nuclear Data Section (IAEA/NDS) in the area of atomic and molecular data is to enhance the competencies of Member States in their research into nuclear fusion through the provision of internationally recommended atomic, molecular, plasma-material interaction and material properties databases. One mechanism by which the IAEA pursues this mission is the Coordinated Research Project (CRP). The present volume of Atomic and Plasma-Material Interaction Data for Fusion contains contributions from participants in the CRP 'Atomic and Molecular Data for Plasma Modelling' (2004-2008). This CRP was concerned with data for processes in the near wall and divertor plasma and plasma-wall interaction in fusion experiments, with focus on cross-sections for molecular reactions. Participants in the CRP came from 14 different institutes, many with strong ties to fusion plasma modelling and experiment. D. Humbert of the Nuclear Data Section was scientific secretary of the CRP. Participants' contributions for this volume were collected and refereed after the conclusion of the CRP

International Fusion Energy Act of 1993. Hearing before the Committee on Energy and Natural Resources, United States Senate, One Hundred Third Congress, First Session on S. 646, May 6, 1993

International Nuclear Information System (INIS)

Anon.

1993-01-01

The text of the bill, International Fusion Energy Act of 1993, is included along with statements from the following: B. Bradley, Senator, NJ; Dr. J. Decker, DOE Office of Energy Research; J. Gavin; Dr. R. Hirsch, Electric Power Research Institute; B. Johnston, Senator, LA; Dr. D. Overskei, General Atomics; Dr. P. Rebut, International Thermonuclear Experimental Reactor; M. Wallop, Senator, WY

Second Symposium on ''Current trends in international fusion research: review and assessment''. Chairman's summary of session

International Nuclear Information System (INIS)

Post, R.F.

1998-01-01

This session began with a keynote speech by B. Coppi of M.I.T., entitled: ''Physics of Fusion Burning Plasmas, Ignition, and Relevant Technology Issues.'' It continued with a second paper on the tokamak approach to fusion, presented by E. Mazzucato of the Princeton Plasma Physics Laboratory, entitled ''High Confinement Plasma Confinement Regime in TFTR Configurations with Reversed Magnetic Shear.'' The session continued with three talks discussing various aspects of the so-called ''Field Reversed Configuration'' (FRC), and concluded with a talk on a more general topic. The first of the three FRC papers, presented by J. Slough of the University of Washington, was entitled ''FRC Reactor for Deep Space Propulsion.'' This paper was followed by a paper by S. Goto of the Plasma Physics Laboratory of Osaka University in Japan, entitled ''Experimental Initiation of Field-Reversed Configuration (FRC) Toward Helium-3 Fusion.'' The third of the FRC papers, authored by H. Mimoto and Y. Tomito of the National Institute for Fusion Science, Nagoya, Japan, and presented by Y. Tomita was entitled ''Helium-3 Fusion Based on a Field-Reversed Configuration.'' The session was concluded with a paper presented by D. Ryutov of the Lawrence Livermore National Laboratory entitled: ''A User Facility for Research on Fusion Systems with Dense Plasmas.''

Portuguese research program on nuclear fusion

International Nuclear Information System (INIS)

Varandas, C.A.F.; Cabral, J.A.C.; Manso, M.E.

1994-01-01

The Portuguese research program on nuclear fusion is presented. The experimental activity associated with the tokamak ISTTOK as well as the work carried out in the frame of international collaboration are summarized. The main technological features of ISTTOK are described along with studies on microwave reflectometry. Future plans are briefly described

Remotely controlled fusion of selected vesicles and living cells: a key issue review

Science.gov (United States)

Bahadori, Azra; Moreno-Pescador, Guillermo; Oddershede, Lene B.; Bendix, Poul M.

2018-03-01

Remote control over fusion of single cells and vesicles has a great potential in biological and chemical research allowing both transfer of genetic material between cells and transfer of molecular content between vesicles. Membrane fusion is a critical process in biology that facilitates molecular transport and mixing of cellular cytoplasms with potential formation of hybrid cells. Cells precisely regulate internal membrane fusions with the aid of specialized fusion complexes that physically provide the energy necessary for mediating fusion. Physical factors like membrane curvature, tension and temperature, affect biological membrane fusion by lowering the associated energy barrier. This has inspired the development of physical approaches to harness the fusion process at a single cell level by using remotely controlled electromagnetic fields to trigger membrane fusion. Here, we critically review various approaches, based on lasers or electric pulses, to control fusion between individual cells or between individual lipid vesicles and discuss their potential and limitations for present and future applications within biochemistry, biology and soft matter.

Overview of Australian activities of fusion neutronics

International Nuclear Information System (INIS)

Zimin, S.; Dewar, R.L.

1999-01-01

The new status of the H-1NF heliac stellarator as a national facility and the signed international implementing agreement on collaboration in the development of the stellarator concept should together be a significant encouragement for further fusion research in Australia. In this report the future of fusion research in Australia is discussed with special attention being paid to the importance of stellarator power plant studies and in particular stellarator fusion neutronics. The main differences between tokamak and stellarator neutronics analyses are identified, namely the neutron wall loading, geometrical modelling and total heating in in-vessel reactor components including toroidal field (TF) coils. An approach to stellarator (TF) coils heating calculations is discussed. This approach is a modification of a previously reported method of total heating calculations in tokamak TF coils. Due to the more complicated nature of stellarator neutronics analyses, simplified approaches to fusion neutronics already developed for tokamaks are expected to be even more important and widely used for designing a conceptual stellarator power plant. (orig.)

International bulletin on atomic and molecular data for fusion. No. 24

International Nuclear Information System (INIS)

Katsonis, K.

1984-01-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided, work in progress is briefly reported: Transport on tokamak plasmas simulation, post collisions of gold ions in helium

International Bulletin on Atomic and Molecular Data for Fusion. No. 28

International Nuclear Information System (INIS)

Hughes, J.G.

1985-03-01

The bulletin presents a selected bibliography (462 literature pieces) on atomic and molecular data relevant to fusion research and technology. It also gives a list of indexed papers, separately on structure and spectra, atomic and molecular collisions, and surface effects

Fusion

CERN Document Server

Mahaffey, James A

2012-01-01

As energy problems of the world grow, work toward fusion power continues at a greater pace than ever before. The topic of fusion is one that is often met with the most recognition and interest in the nuclear power arena. Written in clear and jargon-free prose, Fusion explores the big bang of creation to the blackout death of worn-out stars. A brief history of fusion research, beginning with the first tentative theories in the early 20th century, is also discussed, as well as the race for fusion power. This brand-new, full-color resource examines the various programs currently being funded or p

Genetically controlled fusion, exocytosis and fission of artificial vesicles-a roadmap

DEFF Research Database (Denmark)

Bönzli, Eva; Hadorn, Maik; de Lucrezia, Davide

2011-01-01

were shown to fuse if a special class of viral proteins, termed fusogenic peptides, were added to the external medium (Nomura et al. 2004). In the present work, we intend to develop genetically controlled fusion, fission and exocytosis of vesicles by the synthesis of peptides within vesicles. First, we...... enclosed synthesized peptides in vesicles to induce in a next step fusion of adjacent vesicles, fission and exocytosis of nested vesicles. Second, we will replace the peptides by an enclosed cell-free expression system to internally synthesize fusion peptides. To control the gene expression, different...

Progress in the development of methodology for fusion safety systems studies

International Nuclear Information System (INIS)

Ho, S.K.; Cambi, G.; Ciattaglia, S.; Fujii-e, Y.; Seki, Y.

1994-01-01

The development of fusion safety systems-study methodology, including the aspects of schematic classification of overall fusion safety system, qualitative assessment of fusion system for identification of critical accident scenarios, quantitative analysis of accident consequences and risk for safety design evaluation, and system-level analysis of accident consequences and risk for design optimization, by a consortium of international efforts is presented. The potential application of this methodology into reactor design studies will facilitate the systematic assessment of safety performance of reactor designs and enhance the impacts of safety considerations on the selection of design configurations

Fusion safety program annual report fiscal year 1997

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

1998-01-01

This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2)

Fusion safety program annual report fiscal year 1997

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C. [and others

1998-01-01

This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2).

Collaborations in fusion research

International Nuclear Information System (INIS)

Barnes, D.; Davis, S.; Roney, P.

1995-01-01

This paper reviews current experimental collaborative efforts in the fusion community and extrapolates to operational scenarios for the Tokamak Physics Experiment (TPX) and the International Thermonuclear Experimental Reactor (ITER). Current requirements, available technologies and tools, and problems, issues and concerns are discussed. This paper specifically focuses on the issues that apply to experimental operational collaborations. Special requirements for other types of collaborations, such as theoretical or design and construction efforts, will not be addressed. Our current collaborative efforts have been highly successful, even though the tools in use will be viewed as primitive by tomorrow's standards. An overview of the tools and technologies in today's collaborations can be found in the first section of this paper. The next generation of fusion devices will not be primarily institutionally based, but will be national (TPX) and international (ITER) in funding, management, operation and in ownership of scientific results. The TPX will present the initial challenge of real-time remotely distributed experimental data analysis for a steady state device. The ITER will present new challenges with the possibility of several remote control rooms all participating in the real-time operation of the experimental device. A view to the future of remote collaborations is provided in the second section of this paper

Block-free optical quantum Banyan network based on quantum state fusion and fission

International Nuclear Information System (INIS)

Zhu Chang-Hua; Meng Yan-Hong; Quan Dong-Xiao; Zhao Nan; Pei Chang-Xing

2014-01-01

Optical switch fabric plays an important role in building multiple-user optical quantum communication networks. Owing to its self-routing property and low complexity, a banyan network is widely used for building switch fabric. While, there is no efficient way to remove internal blocking in a banyan network in a classical way, quantum state fusion, by which the two-dimensional internal quantum states of two photons could be combined into a four-dimensional internal state of a single photon, makes it possible to solve this problem. In this paper, we convert the output mode of quantum state fusion from spatial-polarization mode into time-polarization mode. By combining modified quantum state fusion and quantum state fission with quantum Fredkin gate, we propose a practical scheme to build an optical quantum switch unit which is block free. The scheme can be extended to building more complex units, four of which are shown in this paper. (general)

Magnetic compression/magnetized target fusion (MAGO/MTF)

International Nuclear Information System (INIS)

Kirkpatrick, R.C.; Lindemuth, I.R.

1997-03-01

Magnetized Target Fusion (MTF) was reported in two papers at the First Symposium on Current Trends in International Fusion Research. MTF is intermediate between two very different mainline approaches to fusion: Inertial Confinement Fusion (ICF) and magnetic confinement fusion (MCF). The only US MTF experiments in which a target plasma was compressed were the Sandia National Laboratory ''Phi targets''. Despite the very interesting results from that series of experiments, the research was not pursued, and other embodiments of MTF concept such as the Fast Liner were unable to attract the financial support needed for a firm proof of principle. A mapping of the parameter space for MTF showed the significant features of this approach. The All-Russian Scientific Research Institute of Experimental Physics (VNIIEF) has an on-going interest in this approach to thermonuclear fusion, and Los Alamos National Laboratory (LANL) and VNIIEF have done joint target plasma generation experiments relevant to MTF referred to as MAGO (transliteration of the Russian acronym for magnetic compression). The MAGO II experiment appears to have achieved on the order of 200 eV and over 100 KG, so that adiabatic compression with a relatively small convergence could bring the plasma to fusion temperatures. In addition, there are other experiments being pursued for target plasma generation and proof of principle. This paper summarizes the previous reports on MTF and MAGO and presents the progress that has been made over the past three years in creating a target plasma that is suitable for compression to provide a scientific proof of principle experiment for MAGO/MTF

Cassette blanket and vacuum building: key elements in fusion reactor maintenance

International Nuclear Information System (INIS)

Werner, R.W.

1977-01-01

The integration of two concepts important to fusion power reactors is discussed. The first concept is the vacuum building which improves upon the current fusion reactor designs. The second concept, the use of the cassette blanket within the vacuum building environment, introduces four major improvements in blanket design: cassette blanket module, zoning concept, rectangular blanket concept, and internal tritium recovery

Plasma surface interactions in controlled fusion devices

Energy Technology Data Exchange (ETDEWEB)

Ghendrih, Ph.; Becoulet, M.; Costanzo, L. [and others

2000-07-01

This report brings together all the contributions of EURATOM/CEA association to the 14. international conference on plasma surface interactions in controlled fusion devices. 24 papers are presented and they deal mainly with the ergodic divertor and the first wall of Tore-supra tokamak.

Plasma surface interactions in controlled fusion devices

International Nuclear Information System (INIS)

Ghendrih, Ph.; Becoulet, M.; Costanzo, L.

2000-07-01

This report brings together all the contributions of EURATOM/CEA association to the 14. international conference on plasma surface interactions in controlled fusion devices. 24 papers are presented and they deal mainly with the ergodic divertor and the first wall of Tore-supra tokamak

Summary of the international 'Dawson' Symposium on the physics of plasmas

International Nuclear Information System (INIS)

Tajima, T.

1990-12-01

The ''Dawson'' Symposium was held on September 24 and 25, 1990 in honor of John Dawson's 60th birthday to reflect on various physics of plasma that he had pioneered. The international speakers touched on a wide range of subjects: magnetic fusion, laser fusion, isotope separation, computer simulation, basic plasma physics, accelerators and light sources, space physics, and international scientific collaboration. Highlighted in this article are magnetic fusion and laser fusion investigation that Dawson has been engaged in and the reviews of the present status of their development. The impact of the two-component fusion plasma idea, reactor concepts for advanced fuels, hot electron production by lasers and other nonlinear effects in laser fusion are discussed. Dawson's contributions in the allied areas are also reviewed

International bulletin on atomic and molecular data for fusion. No. 27

International Nuclear Information System (INIS)

Hughes, J.G.

1984-12-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent relevent data, summarized in the document, is provided (373 literature pieces). Work in progress on the ionization by electron impact (theoretical results) is also briefly reported on

A Hierarchical Convolutional Neural Network for vesicle fusion event classification.

Science.gov (United States)

Li, Haohan; Mao, Yunxiang; Yin, Zhaozheng; Xu, Yingke

2017-09-01

Quantitative analysis of vesicle exocytosis and classification of different modes of vesicle fusion from the fluorescence microscopy are of primary importance for biomedical researches. In this paper, we propose a novel Hierarchical Convolutional Neural Network (HCNN) method to automatically identify vesicle fusion events in time-lapse Total Internal Reflection Fluorescence Microscopy (TIRFM) image sequences. Firstly, a detection and tracking method is developed to extract image patch sequences containing potential fusion events. Then, a Gaussian Mixture Model (GMM) is applied on each image patch of the patch sequence with outliers rejected for robust Gaussian fitting. By utilizing the high-level time-series intensity change features introduced by GMM and the visual appearance features embedded in some key moments of the fusion process, the proposed HCNN architecture is able to classify each candidate patch sequence into three classes: full fusion event, partial fusion event and non-fusion event. Finally, we validate the performance of our method on 9 challenging datasets that have been annotated by cell biologists, and our method achieves better performances when comparing with three previous methods. Copyright © 2017 Elsevier Ltd. All rights reserved.

Two-dimensional Simulations of Correlation Reflectometry in Fusion Plasmas

International Nuclear Information System (INIS)

Valeo, E.J.; Kramer, G.J.; Nazikian, R.

2001-01-01

A two-dimensional wave propagation code, developed specifically to simulate correlation reflectometry in large-scale fusion plasmas is described. The code makes use of separate computational methods in the vacuum, underdense and reflection regions of the plasma in order to obtain the high computational efficiency necessary for correlation analysis. Simulations of Tokamak Fusion Test Reactor (TFTR) plasma with internal transport barriers are presented and compared with one-dimensional full-wave simulations. It is shown that the two-dimensional simulations are remarkably similar to the results of the one-dimensional full-wave analysis for a wide range of turbulent correlation lengths. Implications for the interpretation of correlation reflectometer measurements in fusion plasma are discussed

Muon nuclear fusion and low temperature nuclear fusion

International Nuclear Information System (INIS)

Nagamine, Kanetada

1990-01-01

Low temperature (or normal temperature) nuclear fusion is one of the phenomena causing nuclear fusion without requiring high temperature. In thermal nuclear fusion, the Coulomb barrier is overcome with the help of thermal energy, but in the low temperature nuclear fusion, the Coulomb barrier is neutralized by the introduction of the particles having larger mass than electrons and negative charges, at this time, if two nuclei can approach to the distance of 10 -13 cm in the neutral state, the occurrence of nuclear fusion reaction is expected. As the mass of the particles is heavier, the neutral region is smaller, and nuclear fusion is easy to occur. The particles to meet this purpose are the electrons within substances and muons. The research on muon nuclear fusion became suddenly active in the latter half of 1970s, the cause of which was the discovery of the fact that the formation of muons occurs resonantly rapidly in D-T and D-D systems. Muons are the unstable elementary particles having the life of 2.2 μs, and they can have positive and negative charges. In the muon catalyzed fusion, the muons with negative charge take part. The principle of the muon catalyzed fusion, its present status and future perspective, and the present status of low temperature nuclear fusion are reported. (K.I.)

Controlled nuclear fusion. Theoretical and technical-physical aspects

International Nuclear Information System (INIS)

Donne, T.; Oomens, N.

1995-01-01

It is stated that the realization of controlled fusion is not only a matter of solving technical problems. Also theoretical research in the field of plasma physics is required. A brief state-of-the-art is given of theoretical and technical-physical aspects of nuclear fusion. Attention is paid to magnetic confinement, the importance of theoretical research, plasma heating, plasma diagnostics, and the control of plasma transport. Throughout the article special attention is paid to the International Thermonuclear Experimental Reactor (ITER) project. 5 figs., 1 tab., 3 refs

The European fusion research and development programme and the ITER Project

International Nuclear Information System (INIS)

Green, B.J.

2004-01-01

The EURATOM fusion R and D programme is a well integrated and co-ordinated programme a good example of a European Research Area. Its goal is 'the joint creation of prototype reactors for power stations to meet the needs of society: operational safety, environmental compatibility, economic viability'. The programme is focussed on the magnetic confinement approach to fusion energy and supports 21 associated laboratories and a range of experimental and fusion technology facilities. The paper will briefly describe this programme and how it is organised and implemented. Its success and that of other national programmes has defined the international ITER Project, which is the next logical step in fusion R and D. The paper will describe ITER, its aims, its design, and the supporting manufacture of prototype components. The European contribution to ITER, as well as the exploitation of the Joint European Torus (JET) and long-term fusion reactor technology R and D are carried out under the European Fusion Development Agreement (EFDA). Finally, the potential advantages of fusion as an energy source will be presented. (author)

Nuclear fusion and fission, and related technologies department: 2007 progress report

International Nuclear Information System (INIS)

2007-12-01

ENEA continues to contribute to broadening plasma physics knowledge as well as to developing the relevant technologies in the framework of the EURATOM-ENEA Association for fusion. This report describes the 2007 research activities carried out by the ENEA Fusion Research Group of the Nuclear Fusion and Fission, and Related Technologies Department (FPN). Other ENEA research groups also contributed to the activities. The following fields were addressed: magnetically confined nuclear fusion (physics and technology), superconductivity and inertial fusion. Planning of the 2007 fusion activities took into account the different scenarios determined by the new organisation of the European programme based on the start of ITER construction. The establishment of the ITER International Organisation and the European Domestic Agency (Fusion for Energy) required a new organisational scheme. This has implied not only the implementation of a more project oriented structure but also the need to launch the constitution of a consortium agreement between the Associations in order to cope with the needs for the design and construction of the components of ITER that require specific know-how, e.g., diagnostics and test blanket module

Assessing a new direction for fusion

International Nuclear Information System (INIS)

Waganer, L.M.

2000-01-01

The principal application proposed for fusion for the past 40 years has been the central station, electrical power generation plant. However, the sizable increases that were forecast for future electrical power demands have not been realized to date. Only coal power plants have been increasing (3%/year) generating capacity (Annual Energy Outlook, 1998) . Likewise, the ability of fusion to deliver economical electrical power has not been credibly postulated, much less demonstrated. Together these two factors have stagnated the commercialization of fusion power. It is now time for a reassessment of what fusion can best do for the world. Fusion, with a practically inexhaustible energy supply, has many unique properties that enable a wide variety of useful products. A study by the ARIES team is underway to review possible fusion applications and assess those with the potential to provide useful and worthwhile new products. A roadmap of possible applications has been developed to assess the utilization of the unique properties of the fusion process. The potential product categories are energy production (fuel, electricity, heat), space propulsion, altered or transmuted material properties (transmutation, waste treatment, tritium production), chemical compound dissociation (waste treatment, ore reduction, refining), and direct use of fusion nuclear products (radiography, lithography, radiotherapy, activation analyses). An evaluation methodology based on the success and failure of previous large, national and international technology development projects was developed to assess and recommend encouraging fusion product applications. A list of significant attributes was defined to describe and characterize projects that are likely to succeed or fail in the global marketplace. These attributes were assigned weights according to their perceived value to the national or global enterprise. An additive utility theory methodology was used to qualitatively evaluate the proposed

International bulletin on atomic and molecular data for fusion. No. 40

International Nuclear Information System (INIS)

Smith, J.J.

1990-03-01

Indexed papers relating to structure and spectra, atomic and molecular collisions, and surface interactions relevant to nuclear fusion are given. Included is the bibliography for all indexed papers. In addition, a list of evaluated numerical atomic databases stored in the IAEA data bank is given

Present status of fusion researches in USA, 4

International Nuclear Information System (INIS)

Yoshikawa, Shoichi; Okabayashi, Michio

1983-01-01

25 years have elapsed since nuclear fusion was published at the second Geneva conference in 1958. During this period, the Plasma Physics Laboratory of Princeton University has achieved the central role in the research on toroidal system nuclear fusion devices. Also the experiment of the large tokamak TFTR started from December, 1982, recorded the longest containment time of 200 ms as the initial data, and toroidal devices look to approach one step close to the scientific verification experiment (Q = 1) of reactors. In the PPPL, in order to perfect the basis required for the realization of nuclear fusion reactors, the experimental and theoretical developments have been carried out. Plasma containment experiment has been advanced successively from stellarater through internal conductor type to tokamak, and in plasma heating, ion cyclotron heating, fast neutral particle injection heating and low region hybrid heating were successfully carried out. As the experimental apparatuses, that for poloidal divertor experiment, Princeton large torus, tokamak fusion test reactor (TFTR) and S-1 spheromak are described. From the theories developed recently, bean type tokamak, heliac-stellarator and nuclear fusion reaction utilizing μ-mesons and nuclear spin are explained. (Kako, I.)

Superconductivity and fusion energy—the inseparable companions

Science.gov (United States)

Bruzzone, Pierluigi

2015-02-01

Although superconductivity will never produce energy by itself, it plays an important role in energy-related applications both because of its saving potential (e.g., power transmission lines and generators), and its role as an enabling technology (e.g., for nuclear fusion energy). The superconducting magnet’s need for plasma confinement has been recognized since the early development of fusion devices. As long as the research and development of plasma burning was carried out on pulsed devices, the technology of superconducting fusion magnets was aimed at demonstrations of feasibility. In the latest generation of plasma devices, which are larger and have longer confinement times, the superconducting coils are a key enabling technology. The cost of a superconducting magnet system is a major portion of the overall cost of a fusion plant and deserves significant attention in the long-term planning of electricity supply; only cheap superconducting magnets will help fusion get to the energy market. In this paper, the technology challenges and design approaches for fusion magnets are briefly reviewed for past, present, and future projects, from the early superconducting tokamaks in the 1970s, to the current ITER (International Thermonuclear Experimental Reactor) and W7-X projects and future DEMO (Demonstration Reactor) projects. The associated cryogenic technology is also reviewed: 4.2 K helium baths, superfluid baths, forced-flow supercritical helium, and helium-free designs. Open issues and risk mitigation are discussed in terms of reliability, technology, and cost.

A roadmap to the realization of fusion energy

International Nuclear Information System (INIS)

Romanelli, Francesco

2013-01-01

With the reduction of CO2 emissions driving future energy policy, fusion can start market penetration beyond 2050 with up to 30% of electricity production by 2100. This requires an ambitious, yet realistic roadmap towards the demonstration of electricity production by 2050. This talk describes the main technical challenges on the path to fusion energy. For all of the challenges candidate solutions have been developed and the goal of the programme is now to demonstrate that they will also work at the scale of reactor. The roadmap has been developed within a goal-oriented approach articulated in eight different Missions. For each Mission the critical aspects for reactor application, the risks and risk mitigation strategies, the level of readiness now and after ITER and the gaps in the programme have been examined with involvement of experts from the ITER International Organization, Fusion for Energy, EFDA Close Support Unites and EFDA Associates. High-level work packages for the roadmap implementation have been prepared and the resources evaluated. ITER is the key facility in the roadmap and its success represents the most important overarching objectives of the EU programme. A demonstration fusion power plant (DEMO), producing net electricity for the grid at the level of a few hundreds MW is foreseen to start operation in the early 2040s. Following ITER, it will be the single step to a commercial fusion power plant. Industry must be involved early in the DEMO definition and design. The evolution of the programme requires that industry progressively shifts its role from that of provider of high-tech components to that of driver of the fusion development. Industry must be able to take full responsibility for the commercial fusion power plant after successful DEMO operation. For this reason, DEMO cannot be defined and designed by research laboratories alone, but requires the full involvement of industry in all technological and systems aspects of the design. Europe

Atomic and plasma-material interaction data for fusion. Vol.1

International Nuclear Information System (INIS)

1991-01-01

The International Atomic Energy Agency, through its Atomic and Molecular Data Unit, coordinates a wide spectrum of programmes for the compilation, evaluation, and generation of atomic, molecular, and plasma-wall interaction data for fusion research. The present, first, volume of Atomic and Plasma-Material Interaction Data for Fusion, contains extended versions of the reviews presented at the IAEA Advisory Group Meeting on Particle-Surface Interaction Data for Fusion, held 19-21 April 1989 at the IAEA Headquarters in Vienna, The plasma-wall interaction processes covered here are those considered most important for the operational performance of magnetic confinement fusion reactors. In addition to processes due to particle impact under normal operation, plasma-wall interaction effects due to off-normal plasma events (disruptions, electron runaway bombardment) are covered, and a summary of the status of data information on these processes is given from the point of view of magnetic fusion reactor design. Refs, figs and tabs

ROK-PRC Cooperation on Laser Fusion Energy

International Nuclear Information System (INIS)

Rhee, Yong Joo; Han, J. M.; Lee, S. M.; Nam, S. M.; Kwan, D. H.; Cha, Y. H.; Baek, S. H.

2009-03-01

International treaties on the reduction of green-house gases are now being established worldwide and Korea is supposed to join these treaties in a near future. Meanwhile the energy production via fission reactors proposed as a solution to this global environmental contamination has still inherent problems in that it also produces long-life radioactive nuclear waste in the long run, causing many serious social issues. Now the ultimate solution in this situation is believed to be the production of energy by the nuclear fusion reaction. In this project, the collaboration regarding high energy laser fusion has been carried out mainly at the Chinese facility such as ShengGuang II (SG II) laser facility, and ultrahigh intensity laser system of KAERI has been used for the small scale laser fusion and production of fast neutrons. Thomson scattering experiment to analyze the fusion plasma, opacity measurement to understand and develop the computer simulation techniques have been carried out at SG II facility, and experiments on implosion reaction which is basic to laser fusion as well as that of X-ray absorption and transmission have been done at the GEKKO XII facility of ILE, Japan. Satisfactory results both for Korea and China have been deduced by the strategy of project such that different approaches for high energy laser fusion and low energy laser fusion were applied. That is, Korean partner could get opportunities of doing experiments at the large laser facilities to get plasma diagnostic technologies and high density simulation technologies, besides the opportunity to participate in the K-C-J collaborative experiments of implosion and X-ray spectroscopy. And Chinese partner could solve their problem related to the laser fusion and neutron generation which were not successful even with their far high 300TW laser system

DEMO concepts and their roles within the fusion programme

International Nuclear Information System (INIS)

Tran, Minh Quang

2007-01-01

In the past years, the international fusion community has developed models of fusion power plants, which were extremely useful in showing the key advantages of fusion energy and pointing out he areas of development. The present view is that between ITER and such power plants (even of ''first of kind'' type), there is a need for one or two intermediate steps. The need to have a ''fast rack'' towards such a fusion reactor, suggested that the steps after ITER, which are usually considered to be a Demonstration power plant followed by a Prototypical one, could be combines into one known as a DEMO. DEMO would then be a device capable of producing electricity, paving the way towards fusion power plants which would be economically viable. This talk outlines the DEMO concepts as the necessary physics and technological extrapolation from the envisaged future steps (ITER, IFMIF) are discussed. It attempts to provide a coverage of the different concepts developed by various countries, The key issues, as foreseen today, and their implications for the programme are highlighted. (orig.)

A New capitalism in Brazil? Fusions & acquisitions on Lula government

Directory of Open Access Journals (Sweden)

José Carlos Martines Belieiro Junior

2014-06-01

Full Text Available This paper aims analyze the phenomenon of fusions and acquisitions of companies in Brazil during the government of ex-president Luis Ignacio Lula da Silva, from 2003 to 2010. The adopted point of view is the one of relations between the State an d the economy trying to investigate what the new role of the private capital in the contemporary Brazil. The basic hypothesis that guide this work is to explain the fusions and acquisitions in a broader context of State support to the process of fusions and acquisitions as a new way of global insertion of Brazilian capitalism in a moment of international competitiveness.

Prospects for toroidal fusion reactors

International Nuclear Information System (INIS)

Sheffield, J.; Galambos, J.D.

1994-01-01

Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate components in engineering, technology, and unit costs, should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, ∼2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges

International bulletin on atomic and molecular data for fusion. No. 23

International Nuclear Information System (INIS)

Katsonis, K.

1983-09-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported (OIV in temperature and density diagnostics, measured cross section for electron impact ionization of Iron and Tungsten)

Recombinant fusion protein of albumin-retinol binding protein inactivates stellate cells

Energy Technology Data Exchange (ETDEWEB)

Choi, Soyoung; Park, Sangeun; Kim, Suhyun [Laboratory of Cellular Oncology, Korea University Graduate School of Medicine, Ansan, Gyeonggi do 425-707 (Korea, Republic of); Lim, Chaeseung [Department of Laboratory Medicine, Korea University Guro Hospital, Seoul 152-703 (Korea, Republic of); Kim, Jungho [Department of Life Science, Sogang University, Seoul 121-742 (Korea, Republic of); Cha, Dae Ryong [Department of Internal Medicine, Korea University Ansan Hospital, Ansan, Gyeonggi do 425-020 (Korea, Republic of); Oh, Junseo, E-mail: ohjs@korea.ac.kr [Laboratory of Cellular Oncology, Korea University Graduate School of Medicine, Ansan, Gyeonggi do 425-707 (Korea, Republic of)

2012-02-03

Highlights: Black-Right-Pointing-Pointer We designed novel recombinant albumin-RBP fusion proteins. Black-Right-Pointing-Pointer Expression of fusion proteins inactivates pancreatic stellate cells (PSCs). Black-Right-Pointing-Pointer Fusion proteins are successfully internalized into and inactivate PSCs. Black-Right-Pointing-Pointer RBP moiety mediates cell specific uptake of fusion protein. -- Abstract: Quiescent pancreatic- (PSCs) and hepatic- (HSCs) stellate cells store vitamin A (retinol) in lipid droplets via retinol binding protein (RBP) receptor and, when activated by profibrogenic stimuli, they transform into myofibroblast-like cells which play a key role in the fibrogenesis. Despite extensive investigations, there is, however, currently no appropriate therapy available for tissue fibrosis. We previously showed that the expression of albumin, composed of three homologous domains (I-III), inhibits stellate cell activation, which requires its high-affinity fatty acid-binding sites asymmetrically distributed in domain I and III. To attain stellate cell-specific uptake, albumin (domain I/III) was coupled to RBP; RBP-albumin{sup domain} {sup III} (R-III) and albumin{sup domain} {sup I}-RBP-albumin{sup III} (I-R-III). To assess the biological activity of fusion proteins, cultured PSCs were used. Like wild type albumin, expression of R-III or I-R-III in PSCs after passage 2 (activated PSCs) induced phenotypic reversal from activated to fat-storing cells. On the other hand, R-III and I-R-III, but not albumin, secreted from transfected 293 cells were successfully internalized into and inactivated PSCs. FPLC-purified R-III was found to be internalized into PSCs via caveolae-mediated endocytosis, and its efficient cellular uptake was also observed in HSCs and podocytes among several cell lines tested. Moreover, tissue distribution of intravenously injected R-III was closely similar to that of RBP. Therefore, our data suggest that albumin-RBP fusion protein comprises

Advanced computational tools and methods for nuclear analyses of fusion technology systems

International Nuclear Information System (INIS)

Fischer, U.; Chen, Y.; Pereslavtsev, P.; Simakov, S.P.; Tsige-Tamirat, H.; Loughlin, M.; Perel, R.L.; Petrizzi, L.; Tautges, T.J.; Wilson, P.P.H.

2005-01-01

An overview is presented of advanced computational tools and methods developed recently for nuclear analyses of Fusion Technology systems such as the experimental device ITER ('International Thermonuclear Experimental Reactor') and the intense neutron source IFMIF ('International Fusion Material Irradiation Facility'). These include Monte Carlo based computational schemes for the calculation of three-dimensional shut-down dose rate distributions, methods, codes and interfaces for the use of CAD geometry models in Monte Carlo transport calculations, algorithms for Monte Carlo based sensitivity/uncertainty calculations, as well as computational techniques and data for IFMIF neutronics and activation calculations. (author)

Minutes of the second meeting of the Joint IFRC/INDC sub-committee on atomic and molecular data for fusion, Vienna, 14 May 1977

International Nuclear Information System (INIS)

Lorenz, A.; Seamon, R.E.

1977-08-01

In this paper the minutes of the second meeting of the Joint IFRC/INDC Subcommittee (International Fusion Research Committee - International Nuclear Data Committee) on Atomic and Molecular Data for Fusion are given

EDITORIAL: Safety aspects of fusion power plants

Science.gov (United States)

Kolbasov, B. N.

2007-07-01

This special issue of Nuclear Fusion contains 13 informative papers that were initially presented at the 8th IAEA Technical Meeting on Fusion Power Plant Safety held in Vienna, Austria, 10-13 July 2006. Following recommendation from the International Fusion Research Council, the IAEA organizes Technical Meetings on Fusion Safety with the aim to bring together experts to discuss the ongoing work, share new ideas and outline general guidance and recommendations on different issues related to safety and environmental (S&E) aspects of fusion research and power facilities. Previous meetings in this series were held in Vienna, Austria (1980), Ispra, Italy (1983), Culham, UK (1986), Jackson Hole, USA (1989), Toronto, Canada (1993), Naka, Japan (1996) and Cannes, France (2000). The recognized progress in fusion research and technology over the last quarter of a century has boosted the awareness of the potential of fusion to be a practically inexhaustible and clean source of energy. The decision to construct the International Thermonuclear Experimental Reactor (ITER) represents a landmark in the path to fusion power engineering. Ongoing activities to license ITER in France look for an adequate balance between technological and scientific deliverables and complying with safety requirements. Actually, this is the first instance of licensing a representative fusion machine, and it will very likely shape the way in which a more common basis for establishing safety standards and policies for licensing future fusion power plants will be developed. Now that ITER licensing activities are underway, it is becoming clear that the international fusion community should strengthen its efforts in the area of designing the next generations of fusion power plants—demonstrational and commercial. Therefore, the 8th IAEA Technical Meeting on Fusion Safety focused on the safety aspects of power facilities. Some ITER-related safety issues were reported and discussed owing to their potential

Fusion performance analysis of plasmas with reversed magnetic shear in the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Ruskov, E.; Bell, M.; Budny, R.V.; McCune, D.C.; Medley, S.S.; Nazikian, R.; Synakowski, E.J.; Goeler, S. von; White, R.B.; Zweben, S.J.

1999-01-01

A case for substantial loss of fast ions degrading the performance of tokamak fusion test reactor plasmas [Phys. Plasmas 2, 2176 (1995)] with reversed magnetic shear (RS) is presented. The principal evidence is obtained from an experiment with short (40 - 70 ms) tritium beam pulses injected into deuterium beam heated RS plasmas [Phys. Rev. Lett. 82, 924 (1999)]. Modeling of this experiment indicates that up to 40% beam power is lost on a time scale much shorter than the beam - ion slowing down time. Critical parameters which connect modeling and experiment are: The total 14 MeV neutron emission, its radial profile, and the transverse stored energy. The fusion performance of some plasmas with internal transport barriers is further deteriorated by impurity accumulation in the plasma core. copyright 1999 American Institute of Physics

Establishment of KAERI Strategy and Organization for Fusion Power Technology Research

International Nuclear Information System (INIS)

Park, Jong Kyun; Kim, Sung Kyu; Park, Keun Bae

2005-04-01

International and domestic status of development activities of nuclear fusion energy technologies are analyzed and summarized. From these results a verifiable R and D strategy is derived which allows purposeful and successful participation in the ITER project and thus enables a domestic technological basis of the commercialization of nuclear fusion energy. A 45-year, three-stage plan is proposed with a detailed plan for the 10-year, 1st stage where a conceptual design of a Korean demonstration fusion power plant (KDEMO) will be developed as well as its key component designs such as breeder blanket

International bulletin on atomic and molecular data for fusion. No. 18

International Nuclear Information System (INIS)

Katsonis, K.

1982-02-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is briefly reported (electron impact excitation of hydrogen-like argon ions, excitation and charge transfer in collisions of Li atoms with alpha particles)

EMP Fusion

OpenAIRE

KUNTAY, Isık

2010-01-01

This paper introduces a novel fusion scheme, called EMP Fusion, which has the promise of achieving breakeven and realizing commercial fusion power. The method is based on harnessing the power of an electromagnetic pulse generated by the now well-developed flux compression technology. The electromagnetic pulse acts as a means of both heating up the plasma and confining the plasma, eliminating intermediate steps. The EMP Fusion device is simpler compared to other fusion devices and this reduces...

Goals, challenges, and successes of managing fusion activated materials

International Nuclear Information System (INIS)

El-Guebaly, L.; Massaut, V.; Zucchetti, M.; Tobita, K.; Cadwallader, L.

2007-01-01

After decades of designing magnetic and inertial fusion power plants, it is timely to develop a new framework for managing the activated materials generated during plant operation and after decommissioning - a framework that takes into account the lessons learned from numerous international fusion and fission studies and the environmental, political, and present reality in the U.S., EU, and Japan. Since the inception of the fusion projects in the early 1970s, the majority of power plant designs have focused on the disposal of active materials in geological repositories as the main option for handling the replaceable and life-of-plant components, adopting the preferred fission waste management approach. It is becoming evident that future regulations for geological burial will be upgraded to assure tighter environmental controls. Along with the political difficulty of constructing new repositories worldwide, the current reality suggests reshaping all aspects of handling the continual stream of fusion active materials. There is a growing international effort in support of this new trend. Beginning in the mid 1990s and continuing to the present, fusion designs developed in Europe, U.S., and Japan have examined replacing the disposal option with more environmentally attractive approaches, redirecting their attention to recycling and clearance while continuing the development of materials with low activation potential. These options became more technically feasible in recent years with the development of radiation-hardened remote handling (RH) tools and the introduction of the clearance category for slightly radioactive materials by national and international nuclear agencies. We applied all scenarios to selected fusion studies. While recycling and clearance appeared technically attractive and judged, in some cases, a must requirement to control the radwaste stream, the disposal scheme emerged as the preferred option for specific components for several reasons, including

Fusion research as a subject of parliamentary technology assessment

International Nuclear Information System (INIS)

Gruenwald, R.; Grunwald, A.; Oertel, D.

2004-01-01

Fusion research is an internationally interlaced precautionary activity in the public interest and with public support. Parliamentary technology assessment serves to consult parliament in upcoming opinion- and decision-making processes.The task in this case is to give a comprehensible account of the status of development, to consider the different impacts and consequences of fusion, and to provide options for actions by parliament. The major methodological challenge consists in dealing with the uncertainty of knowledge in view of the long time scales involved. (orig.)

Snowmass 2002: The Fusion Energy Sciences Summer Study

International Nuclear Information System (INIS)

Sauthoff, N.; Navratil, G.; Bangerter, R.

2002-01-01

The Fusion Summer Study 2002 will be a forum for the critical technical assessment of major next-steps in the fusion energy sciences program, and will provide crucial community input to the long-range planning activities undertaken by the DOE [Department of Energy] and the FESAC [Fusion Energy Sciences Advisory Committee]. It will be an ideal place for a broad community of scientists to examine goals and proposed initiatives in burning plasma science in magnetic fusion energy and integrated research experiments in inertial fusion energy. This meeting is open to every member of the fusion energy science community and significant international participation is encouraged. The objectives of the Fusion Summer Study are three: (1) Review scientific issues in burning plasmas to establish the basis for the following two objectives and to address the relations of burning plasma in tokamaks to innovative magnetic fusion energy (MFE) confinement concepts and of ignition in inertial fusion energy (IFE) to integrated research facilities. (2) Provide a forum for critical discussion and review of proposed MFE burning plasma experiments (e.g., IGNITOR, FIRE, and ITER) and assess the scientific and technological research opportunities and prospective benefits of these approaches to the study of burning plasmas. (3) Provide a forum for the IFE community to present plans for prospective integrated research facilities, assess present status of the technical base for each, and establish a timetable and technical progress necessary to proceed for each. Based on significant preparatory work by the fusion community prior to the July Snowmass meeting, the Snowmass working groups will prepare a draft report that documents the scientific and technological benefits of studies of burning plasmas. The report will also include criteria by which the benefits of each approach to fusion science, fusion engineering/technology, and the fusion development path can be assessed. Finally, the report

Multiple generations of high salinity formation water in the Triassic Sherwood Sandstone: Wytch Farm oilfield, onshore UK

International Nuclear Information System (INIS)

Worden, R.H.; Manning, D.A.C.; Bottrell, S.H.

2006-01-01

The origin and heterogeneity of oilfield formation water in the Lower Triassic Sherwood Sandstone at Wytch Farm in the Wessex Basin, UK, have been investigated using production data, detailed water geochemistry and O, S and H stable isotope data. The formation waters are highly saline, NaCl-type brines with TDS values of up to 230,000mg/L. There is a general decrease in salinity from the flanks of the field to the crest with Cl - decreasing from about 136,000 to 109,000mg/L. The Cl/Br ratio of the water shows that salinity was largely derived from the dissolution of Upper Triassic continental evaporites found off-structure to the west and north of the field. The water in the field had a meteoric source although variation in δ 2 H values suggests that there may be meteoric waters of different ages in the oilfield, reflecting recharge under different palaeoclimatic conditions. At the crest of the field, aqueous SO 4 2- resulted from dissolution of anhydrite in the reservoir. In contrast, in other parts of the field there is an indication that some of the dissolved SO 4 2- was derived from oxidation of pyrite at some point on the recharge path of meteoric water to the field. There were two meteoric influx events bringing different Cl - concentrations and different δ 2 H values. The first was probably before the Eocene oil influx and could have occurred in the Lower Cretaceous or early Tertiary. The second meteoric influx event probably occurred after or during oil migration into the Wytch Farm structure since the second meteoric water is found at the flanks of the field adjacent to the regions where salt is found in the stratigraphy. The preservation of heterogeneities in oilfield formation water compositions suggests that there has been little aqueous fluid movement or diffusive flux for over 40 million years. Mass flux has been restricted by density stratification within the aquifer and the very low effective permeability for the aqueous phase in the oil

Accelerators for Fusion Materials Testing

Science.gov (United States)

Knaster, Juan; Okumura, Yoshikazu

with the International Fusion Materials Irradiation Facility (IFMIF) under discussion at the time. Worldwide technological efforts are maturing soundly and the time for a fusion-relevant neutron source has arrived according to world fusion roadmaps; if decisions are taken we could count the next decade with a powerful source of 14 MeV neutrons thanks to the expected significant results of the Engineering Validation and Engineering Design Activity (EVEDA) phase of the IFMIF project. The accelerator know-how has matured in all possible aspects since the times of FMIT conception in the 1970s; today, operating 125 mA deuteron beam at 40 MeV in CW with high availabilities seems feasible thanks to the understanding of the beam halo physics and the three main technological breakthroughs in accelerator technology: (1) the ECR ion source for light ions developed at Chalk River Laboratories in the early 1990s, (2) the RFQ operation of H+ in CW with 100 mA demonstrated by LEDA in LANL in the late 1990s, and (3) the growing maturity of superconducting resonators for light hadrons and low β beams achieved in recent years.

Thermonuclear fusion

International Nuclear Information System (INIS)

Weisse, J.

2000-01-01

This document takes stock of the two ways of thermonuclear fusion research explored today: magnetic confinement fusion and inertial confinement fusion. The basic physical principles are recalled first: fundamental nuclear reactions, high temperatures, elementary properties of plasmas, ignition criterion, magnetic confinement (charged particle in a uniform magnetic field, confinement and Tokamak principle, heating of magnetized plasmas (ohmic, neutral particles, high frequency waves, other heating means), results obtained so far (scale laws and extrapolation of performances, tritium experiments, ITER project), inertial fusion (hot spot ignition, instabilities, results (Centurion-Halite program, laser experiments). The second part presents the fusion reactor and its associated technologies: principle (tritium production, heat source, neutron protection, tritium generation, materials), magnetic fusion (superconducting magnets, divertor (role, principle, realization), inertial fusion (energy vector, laser adaptation, particle beams, reaction chamber, stresses, chamber concepts (dry and wet walls, liquid walls), targets (fabrication, injection and pointing)). The third chapter concerns the socio-economic aspects of thermonuclear fusion: safety (normal operation and accidents, wastes), costs (costs structure and elementary comparison, ecological impact and external costs). (J.S.)

Fusion energy 2002. 19th conference proceedings

International Nuclear Information System (INIS)

2003-01-01

This CD-ROM contains the proceedings of the 19th International Conference on Fusion energy 2002, held in Lyon, France, on 14-19 October 2002. The CD-Rom contains HTML files for navigation via WEB brouser, the papers in PDF and Acrobat Reader 5 for Windows, Mac-OS and UNIX

STARPOWER: An IMAX reg-sign Film on Fusion

International Nuclear Information System (INIS)

Kirsch, J.W.

1995-01-01

The Reuben H. Fleet Space Theater and Science Center and Four Square Productions, Inc. are producing STARPOWER, a new IMAX/OMNIMAX reg-sign film about thermonuclear fusion. The film's storyline will link our understanding of fusion as the power source of the stars with our current quest to develop a practical machine that uses fusion to produce electric power. The goal is to reach the world-wide audience of 40,000,000 people who visit IMAX/OMNIMAX reg-sign theaters each year, about half of which are in the United States and Canada. This document is the final report on a project to research and develop the concept. It was supported by grants from the Department of Energy (Museum Science Education Program), the International Space Theater Consortium (ISTC's Film Development Fund), and contributions by the Fleet Center and Four Square Productions. The report describes the development of the film's educational objectives, findings on the current state of fusion research, film treatments and marketing research for the project, preparation of the project prospectus, and planned next steps

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

1993-01-01

This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

Design of intense neutron source for fusion material study and the role of universities

International Nuclear Information System (INIS)

Ishino, Shiori

1993-01-01

Need and requirement for the intense neutron source for fusion materials study have been discussed for many years. Recently, international climate has been becoming gradually maturing to consider this problem more seriously because of the recognition of crucial importance of solving materials problems for fusion energy development. The present symposium was designed to discuss the problems associated with the intense neutron source for material irradiation studies which will have a potential for the National Institute for Fusion Science to become one of the important future research areas. The symposium comprises five sessions; first, the role of materials research in fusion development strategies was discussed followed by a brief summary of current IFMIF (International Fusion Materials Irradiation Facility) activity. Despite the pressing need for intense fusion neutron source, currently available neutron sources are reactor or accelerator based sources of which FFTF and LASREF were discussed. Then, various concepts of intense neutron source candidates were presented including ESNIT, which are currently under design by JAERI. In the fourth session, discussions were made on the study of materials with the intense neutron source from the viewpoint of materials scientists and engineers as the user of the facility. This is followed by discussions on the role of universities from the two stand points, namely, fusion irradiation studies and fusion materials development. Finally summary discussions were made by the participants, indicating important role fundamental studies in universities for the full utilization of irradiation data and the need of pure 14 MeV neutron source for fundamental studies together with the intense surrogate neutron sources. (author)

International bulletin on atomic and molecular data for fusion. No. 35

International Nuclear Information System (INIS)

Smith, J.J.

1987-05-01

The bulletin provides information on atomic and molecular data for fusion research. In Part I the indexed papers are listed separately for structure and spectra, atomic and molecular collisions, and surface effects. Part II contains all the bibliographic data for both indexed and non-indexed references (536 references). An author index is included

Cryogenic system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1992-01-01

This report presents a review of cryogenic system operating experiences, from particle accelerator, fusion experiment, space research, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of cryogenic component failure rates and accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with cryogenic systems are discussed, including ozone formation, effects of spills, and modeling spill behavior. This information should be useful to fusion system designers and safety analysts, such as the team working on the International Thermonuclear Experimental Reactor design

Fusion neutronics

CERN Document Server

Wu, Yican

2017-01-01

This book provides a systematic and comprehensive introduction to fusion neutronics, covering all key topics from the fundamental theories and methodologies, as well as a wide range of fusion system designs and experiments. It is the first-ever book focusing on the subject of fusion neutronics research. Compared with other nuclear devices such as fission reactors and accelerators, fusion systems are normally characterized by their complex geometry and nuclear physics, which entail new challenges for neutronics such as complicated modeling, deep penetration, low simulation efficiency, multi-physics coupling, etc. The book focuses on the neutronics characteristics of fusion systems and introduces a series of theories and methodologies that were developed to address the challenges of fusion neutronics, and which have since been widely applied all over the world. Further, it introduces readers to neutronics design’s unique principles and procedures, experimental methodologies and technologies for fusion systems...

High Level Information Fusion (HLIF) with nested fusion loops

Science.gov (United States)

Woodley, Robert; Gosnell, Michael; Fischer, Amber

2013-05-01

Situation modeling and threat prediction require higher levels of data fusion in order to provide actionable information. Beyond the sensor data and sources the analyst has access to, the use of out-sourced and re-sourced data is becoming common. Through the years, some common frameworks have emerged for dealing with information fusion—perhaps the most ubiquitous being the JDL Data Fusion Group and their initial 4-level data fusion model. Since these initial developments, numerous models of information fusion have emerged, hoping to better capture the human-centric process of data analyses within a machine-centric framework. 21st Century Systems, Inc. has developed Fusion with Uncertainty Reasoning using Nested Assessment Characterizer Elements (FURNACE) to address challenges of high level information fusion and handle bias, ambiguity, and uncertainty (BAU) for Situation Modeling, Threat Modeling, and Threat Prediction. It combines JDL fusion levels with nested fusion loops and state-of-the-art data reasoning. Initial research has shown that FURNACE is able to reduce BAU and improve the fusion process by allowing high level information fusion (HLIF) to affect lower levels without the double counting of information or other biasing issues. The initial FURNACE project was focused on the underlying algorithms to produce a fusion system able to handle BAU and repurposed data in a cohesive manner. FURNACE supports analyst's efforts to develop situation models, threat models, and threat predictions to increase situational awareness of the battlespace. FURNACE will not only revolutionize the military intelligence realm, but also benefit the larger homeland defense, law enforcement, and business intelligence markets.

Fusion power plant for water desalination and reuse

International Nuclear Information System (INIS)

Borisov, A.A.; Desjatov, A.V.; Izvolsky, I.M.; Serikov, A.G.; Smirnov, V.P.; Smirnov, Yu.N.; Shatalov, G.E.; Sheludjakov, S.V.; Vasiliev, N.N.; Velikhov, E.P.

2001-01-01

Development of industry and agriculture demands a huge fresh water consumption. Exhaust of water sources together with pollution arises a difficult problem of population, industry, and agriculture water supply. Request for additional water supply in next 50 years is expected from industrial and agricultural sectors of many countries in the world. The presented study of fusion power plant for water desalination and reuse is aimed to widen a range of possible fusion industrial applications. Fusion offers a safe, long-term source of energy with abundant resources and major environmental advantages. Thus fusion can provide an attractive energy option to society in the next century. Fusion power tokamak reactor based on RF DEMO-S project [Proc. ISFNT-5 (2000) in press; Conceptual study of RF DEMO-S fusion reactor (2000)] was chosen as an energy source. A steady state operation mode is considered with thermal power of 4.0 GW. The reactor has to operate in steady-state plasma mode with high fraction of bootstrap current. Average plant availability of ∼0.7 is required. A conventional type of water cooled blanket is the first choice, helium or lithium coolants are under consideration. Desalination plant includes two units: reverse osmosis and distillation. Heat to electricity conversion schemes is optimized fresh water production and satisfy internal plant electricity demand The plant freshwater capacity is ∼6000000 m 3 per day. Fusion power plant of this capacity can provide a region of a million populations with fresh water, heat and electricity

Fusion power plant for water desalination and reuse

Energy Technology Data Exchange (ETDEWEB)

Borisov, A.A.; Desjatov, A.V.; Izvolsky, I.M.; Serikov, A.G.; Smirnov, V.P.; Smirnov, Yu.N.; Shatalov, G.E.; Sheludjakov, S.V.; Vasiliev, N.N. E-mail: vasiliev@nfi.kiae.ru; Velikhov, E.P

2001-11-01

Development of industry and agriculture demands a huge fresh water consumption. Exhaust of water sources together with pollution arises a difficult problem of population, industry, and agriculture water supply. Request for additional water supply in next 50 years is expected from industrial and agricultural sectors of many countries in the world. The presented study of fusion power plant for water desalination and reuse is aimed to widen a range of possible fusion industrial applications. Fusion offers a safe, long-term source of energy with abundant resources and major environmental advantages. Thus fusion can provide an attractive energy option to society in the next century. Fusion power tokamak reactor based on RF DEMO-S project [Proc. ISFNT-5 (2000) in press; Conceptual study of RF DEMO-S fusion reactor (2000)] was chosen as an energy source. A steady state operation mode is considered with thermal power of 4.0 GW. The reactor has to operate in steady-state plasma mode with high fraction of bootstrap current. Average plant availability of {approx}0.7 is required. A conventional type of water cooled blanket is the first choice, helium or lithium coolants are under consideration. Desalination plant includes two units: reverse osmosis and distillation. Heat to electricity conversion schemes is optimized fresh water production and satisfy internal plant electricity demand The plant freshwater capacity is {approx}6000000 m{sup 3} per day. Fusion power plant of this capacity can provide a region of a million populations with fresh water, heat and electricity.

Nuclear Fusion Award 2009 speech Nuclear Fusion Award 2009 speech

Science.gov (United States)

Sabbagh, Steven Anthony

2011-01-01

This is an exceptional moment in my career, and so I want to thank all of my teachers, colleagues and mentors who have made this possible. From my co-authors and myself, many thanks to the International Atomic Energy Agency, IOP Publishing, the Nuclear Fusion journal team, and the selection committee for the great honor of receiving this award. Also gratitude to Kikuchi-sensei, not only for the inventive and visionary creation of this award, but also for being a key mentor dating back to his efforts in producing high neutron output in JT-60U. It was also a great honor to receive the award directly from IAEA Deputy Director General Burkart during the 23rd IAEA Fusion Energy Conference in Daejeon. Receiving the award at this venue is particularly exciting as Daejeon is home to the new, next-generation KSTAR tokamak device that will lead key magnetic fusion research areas going forward. I would also like to thank the mayor of Daejeon, Dr Yum Hong-Chul, and all of the meeting organizers for giving us all a truly spectacular and singular welcoming event during which the award was presented. The research leading to the award would not have been possible without the support of the US Department of Energy, and I thank the Department for the continued funding of this research. Special mention must be made to a valuable co-author who is no longer with us, Professor A. Bondeson, who was a significant pioneer in resistive wall mode (RWM) research. I would like to thank my wife, Mary, for her infinite patience and encouragement. Finally, I would like to personally thank all of you that have approached and congratulated me directly. There are no units to measure how important your words have been in this regard. When notified that our paper had been shortlisted for the 2009 Nuclear Fusion Award, my co-authors responded echoing how I felt—honored to be included in such a fine collection of research by colleagues. It was unfathomable—would this paper follow the brilliant work

Development and verification of remote research environment based on 'Fusion research grid'

International Nuclear Information System (INIS)

Iba, Katsuyuki; Ozeki, Takahisa; Totsuka, Toshiyuki; Suzuki, Yoshio; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Suzuki, Mitsuhiro; Hamamatsu, Kiyotaka; Kiyono, Kimihiro

2008-01-01

'Fusion research grid' is a concept that unites scientists and let them collaborate effectively against their difference in time zone and location in a nuclear fusion research. Fundamental technologies of 'Fusion research grid' have been developed at JAEA in the VizGrid project under the e-Japan project at the Ministry of Education, Culture, Sports, Science and Technology (MEXT). We are conscious of needs to create new systems that assist researchers with their research activities because remote collaborations have been increasing in international projects. Therefore we have developed prototype remote research environments for experiments, diagnostics, analyses and communications based on 'Fusion research grid'. All users can access these environments from anywhere because 'Fusion research grid' does not require a closed network like Super SINET to maintain security. The prototype systems were verified in experiments at JT-60U and their availability was confirmed

Fusion of Selected Cells and Vesicles Mediated by Optically Trapped Plasmonic Nanoparticles

DEFF Research Database (Denmark)

Bahadori, Azra

. In this work, we introduce a novel and extremely flexible physical method which can trigger membrane fusion in a highly selective manner not only between synthetic GUVs of different compositions, but also between live cells which remain viable after fusion. Optical tweezers’ laser (1064 nm) is used to position....... The concept of cellular delivery is also known as targeted drug delivery and is quite a hot research topic internationally. Therefore, there have been efforts to develop various chemical molecules, proteins/peptides and physical approaches to trigger membrane fusion between synthetic giant unilamellar...... and merging of the two membranes results in merging the two membranes thereby completes the fusion. Complete fusion is associated with lipid mixing and lumen mixing which are both imaged by a high resolution confocal microscope. The confocal imaging enables quantification of the associated lipid mixing...

Muon-catalyzed fusion: A new direction in fusion research

International Nuclear Information System (INIS)

Jones, S.E.

1986-01-01

In four years of intensive research, muon-catalyzed fusion has been raised from the level of a scientific curiosity to a potential means of achieving clean fusion energy. This novel approach to fusion is based on the fact that a sub-atomic particle known as a ''muon'' can induce numerous energy-releasing fusion reactions without the need for high temperatures or plasmas. Thus, the muon serves as a catalyst to facilitate production for fusion energy. The success of the research effort stems from the recent discovery of resonances in the reaction cycle which make the muon-induced fusion process extremely efficient. Prior estimates were pessimistic in that only one fusion per muon was expected. In that case energy balance would be impossible since energy must be invested to generate the muons. However, recent work has gone approximately half-way to energy balance and further improvements are being worked on. There has been little time to assess the full implications of these discoveries. However, various ways to use muon-catalyzed fusion for electrical power production are now being explored

Muon-catalyzed fusion: a new direction in fusion research

International Nuclear Information System (INIS)

Jones, S.E.

1986-01-01

In four years of intensive research, muon-catalyzed fusion has been raised from the level of a scientific curiosity to a potential means of achieving clean fusion energy. This novel approach to fusion is based on the fact that a sub-atomic particle known as a ''muon'' can induce numerous energy-releasing fusion reactions without the need for high temperatures or plasmas. Thus, the muon serves as a catalyst to facilitate production for fusion energy. The success of the research effort stems from the recent discovery of resonances in the reaction cycle which make the muon-induced fusion process extremely efficient. Prior estimates were pessimistic in that only one fusion per muon was expected. In that case energy balance would be impossible since energy must be invested to generate the muons. However, recent work has gone approximately half-way to energy balance and further improvements are being worked on. There has been little time to assess the full implications of these discoveries. However, various ways to use muon-catalyzed fusion for electrical power production are now being explored

International Bulletin on Atomic and Molecular Data for Fusion. No. 36

International Nuclear Information System (INIS)

Smith, J.J.

1987-10-01

The bulletin provides information on atomic and molecular data relevant for fusion research. In Part I the indexed papers are listed separately for structure and spectra, atomic and molecular collisions and surface interactions. Part II contains all the bibliographic data for both the indexed and non-indexed references (555 references). An author index is included

International bulletin on atomic and molecular data for fusion. No. 39

International Nuclear Information System (INIS)

Smith, J.J.

1989-07-01

The Bulletin provides information on atomic and molecular data relevant for fusion research. In part I the indexed papers are listed separately for structure and spectra, atomic and molecular collisions, and surface interactions. Part II contains all the bibliographic data for both the indexed and non-indexed references (514 references). An author index is included

International bulletin on atomic and molecular data for fusion. No. 38

International Nuclear Information System (INIS)

Smith, J.J.

1989-01-01

The Bulletin provides information on atomic and molecular data relevant for fusion research. In Part I the indexed papers are listed separately for structure and spectra, atomic and molecular collisions and surface interactions. Part II contains all the bibliographic data for both the indexed and non-indexed references (654 references). An author index is included

Fusion breeder

International Nuclear Information System (INIS)

Moir, R.W.

1982-01-01

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be made and tell why it should be made, and to outline specific research and development goals so that the fusion breeder will be developed in time to meet fissile fuel needs

Fire protection system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor

Fire protection system operating experience review for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor.

The fusion evaluated data library (FENDL) its processing and related benchmark calculations

International Nuclear Information System (INIS)

Muir, D.W.

1989-01-01

FENDL is a nuclear data library being assembled by the IAEA Nuclear Data Section, in support of a variety of national and international fusion research projects. Notable examples of such projects are the International Experimental Thermonuclear Reactor (ITER), Fusion Engineering Reactor (FER, Japan), and the Next European Torus (NET). The development of the FENDL library is an approved program of the IAEA and is supported by several IAEA Coordinated Research Programs. It appears to me that the planned FENDL data processing and data testing efforts will be a shared effort, with significant contributions coming from the IAEA itself and from the participating research laboratories and data centers

EU socio-economic research on fusion: Findings and program

International Nuclear Information System (INIS)

Tosato, G.C.

2003-01-01

In 1997 the European Commission launched a Socio-Economic Research program to study under which conditions future fusion power plants may become competitive, compatible with the energy supply system and acceptable for the public. It has been shown, among others, that: 1) local communities are ready to support the construction of an experimental fusion facility, if appropriate communication and awareness campaigns are carried out; 2) since the externalities are much lower than for competitors, fusion power plants may become the major producer of base load electricity at the end of the century in Europe, if climate changes have to be mitigated, if the construction of new nuclear fission power plants continues to be constrained and if nuclear fusion power plants become commercially available in 2050. Cooperating with major international organizations, the program for next year aims to demonstrating, through technical economic programming models and global multi-regional energy environmental scenarios, that the potential global benefits of fusion power plants in the second half of the century largely outdo the RD and D costs borne in the first half to make it available. Making the public aware of such benefits through field experiences will be part of the program. (author)

Achievement of solid-state plasma fusion ('Cold-Fusion')

International Nuclear Information System (INIS)

Arata, Yoshiaki; Zhang, Yue-Chang

1995-01-01

Using a 'QMS' (Quadrupole Mass Spectrometer), the authors detected a significantly large amount (10 20 -10 21 [cm -3 ]) of helium ( 2 4 He), which was concluded to have been produced by a deuterium nuclear reaction within a host solid. These results were found to be fully repeatable and supported the authors' proposition that solid state plasma fusion ('Cold Fusion') can be generated in energetic deuterium Strongly Coupled Plasma ('SC-plasma'). This fusion reaction is thought to be sustained by localized 'Latticequake' in a solid-state media with the deuterium density equivalent to that of the host solid. While exploring this basic proposition, the characteristic differences when compared with ultra high temperature-state plasma fusion ('Hot Fusion') are clarified. In general, the most essential reaction product in both types of the deuterium plasma fusion is considered to be helium, irrespective of the 'well-known and/or unknown reactions', which is stored within the solid-state medium in abundance as a 'Residual Product', but which generally can not enter into nor be released from host-solid at a room temperature. Even measuring instruments with relatively poor sensitivity should be able to easily detect such residual helium. An absence of residual helium means that no nuclear fusion reaction has occurred, whereas its presence provides crucial evidence that nuclear fusion has, in fact, occurred in the solid. (author)

Fusion Implementation

International Nuclear Information System (INIS)

Schmidt, J.A.

2002-01-01

If a fusion DEMO reactor can be brought into operation during the first half of this century, fusion power production can have a significant impact on carbon dioxide production during the latter half of the century. An assessment of fusion implementation scenarios shows that the resource demands and waste production associated with these scenarios are manageable factors. If fusion is implemented during the latter half of this century it will be one element of a portfolio of (hopefully) carbon dioxide limiting sources of electrical power. It is time to assess the regional implications of fusion power implementation. An important attribute of fusion power is the wide range of possible regions of the country, or countries in the world, where power plants can be located. Unlike most renewable energy options, fusion energy will function within a local distribution system and not require costly, and difficult, long distance transmission systems. For example, the East Coast of the United States is a prime candidate for fusion power deployment by virtue of its distance from renewable energy sources. As fossil fuels become less and less available as an energy option, the transmission of energy across bodies of water will become very expensive. On a global scale, fusion power will be particularly attractive for regions separated from sources of renewable energy by oceans

Tritium-management requirements for D-T fusion reactors (ETF, INTOR, FED)

International Nuclear Information System (INIS)

Finn, P.A.; Clemmer, R.G.; Misra, B.

1981-10-01

The successful operation of D-T fusion reactors will depend on the development of safe and reliable tritium-containment and fuel-recycle systems. The tritium handling requirements for D-T reactors were analyzed. The reactor facility was then designed from the viewpoint of tritium management. Recovery scenarios after a tritium release were generated to show the relative importance of various scenarios. A fusion-reactor tritium facility was designed which would be appropriate for all types of plants from the Engineering Test Facility (ETF), the International Tokamak Reactor (INTOR), and the Fusion Engineering Device (FED) to the full-scale power plant epitomized by the STARFIRE design

EDITORIAL: Plasma Surface Interactions for Fusion

Science.gov (United States)

2006-05-01

Because plasma-boundary physics encompasses some of the most important unresolved issues for both the International Thermonuclear Experimental Reactor (ITER) project and future fusion power reactors, there is a strong interest in the fusion community for better understanding and characterization of plasma wall interactions. Chemical and physical sputtering cause the erosion of the limiters/divertor plates and vacuum vessel walls (made of C, Be and W, for example) and degrade fusion performance by diluting the fusion fuel and excessively cooling the core, while carbon redeposition could produce long-term in-vessel tritium retention, degrading the superior thermo-mechanical properties of the carbon materials. Mixed plasma-facing materials are proposed, requiring optimization for different power and particle flux characteristics. Knowledge of material properties as well as characteristics of the plasma material interaction are prerequisites for such optimizations. Computational power will soon reach hundreds of teraflops, so that theoretical and plasma science expertise can be matched with new experimental capabilities in order to mount a strong response to these challenges. To begin to address such questions, a Workshop on New Directions for Advanced Computer Simulations and Experiments in Fusion-Related Plasma Surface Interactions for Fusion (PSIF) was held at the Oak Ridge National Laboratory from 21 to 23 March, 2005. The purpose of the workshop was to bring together researchers in fusion related plasma wall interactions in order to address these topics and to identify the most needed and promising directions for study, to exchange opinions on the present depth of knowledge of surface properties for the main fusion-related materials, e.g., C, Be and W, especially for sputtering, reflection, and deuterium (tritium) retention properties. The goal was to suggest the most important next steps needed for such basic computational and experimental work to be facilitated

One-Dimensional Burn Dynamics of Plasma-Jet Magneto-Inertial Fusion

Science.gov (United States)

Santarius, John

2009-11-01

This poster will discuss several issues related to using plasma jets to implode a Magneto-Inertial Fusion (MIF) liner onto a magnetized plasmoid and compress it to fusion-relevant temperatures [1]. The problem of pure plasma jet convergence and compression without a target present will be investigated. Cases with a target present will explore how well the liner's inertia provides transient plasma stability and confinement. The investigation uses UW's 1-D Lagrangian radiation-hydrodynamics code, BUCKY, which solves single-fluid equations of motion with ion-electron interactions, PdV work, table-lookup equations of state, fast-ion energy deposition, and pressure contributions from all species. Extensions to the code include magnetic field evolution as the plasmoid compresses plus dependence of the thermal conductivity and fusion product energy deposition on the magnetic field.[4pt] [1] Y.C. F. Thio, et al.,``Magnetized Target Fusion in a Spheroidal Geometry with Standoff Drivers,'' in Current Trends in International Fusion Research, E. Panarella, ed. (National Research Council of Canada, Ottawa, Canada, 1999), p. 113.

Development of lithium target system in engineering validation and engineering design activity of the international fusion materials irradiation facility (IFMIF/EVEDA)

International Nuclear Information System (INIS)

Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Ida, Mizuho; Kanemura, Takuji; Watanabe, Kazuyoshi; Fujishiro, Kouji; Edao, Yuuki; Niitsuma, Shigeto; Kimura, Haruyuki; Fukada, Satoshi; Hiromoto, Tetsushi; Shigeharu, Satoshi; Yagi, Jyuro; Furukawa, Tomohiro; Hirakawa, Yasushi; Suzuki, Akihiro; Terai, Takayuki; Horiike, Hiroshi; Hoashi, Eiji; Suzuki, Sachiko; Yamaoka, Nobuo; Serizawa, Hisashi; Kawahito, Yosuke; Tsuji, Yoshiyuki; Furuya, Kazuyuki; Takeo, Fumio

2012-01-01

Engineering validation and engineering design activity (EVEDA) for the international fusion materials irradiation facility (IFMIF) has been conducted since 2007. Research and development of the Lithium target facility is an important part of this activity. We constructed a world largest liquid Lithium test loop with a capacity of 5000 L in 2010 and successfully completed the first stage validation tests (functional tests of components and Lithium flow test (flow velocity 15 m/s at the target). In the present article, recent results of the EVEDA activity for the Lithium target facility and related technologies on liquid Lithium are reviewed. (author)

International bulletin on atomic and molecular data for fusion. No. 25

International Nuclear Information System (INIS)

Katsonis, K.

1984-06-01

This bulletin deals with atomic and molecular data for fusion. A bibliography for the most recent data presented in the document is provided. Work in progress is also briefly reported (Collision strengths and recombination coefficients for ions of C,N,O; Reactions between ions and atomic hydrogen; Cross sections for electron impact ionisation of Ne + , Ti + and Ni + ions)

Fusion--fission hybrid concepts for laser-induced fusion

International Nuclear Information System (INIS)

Maniscalco, J.

1976-01-01

Fusion-fission hybrid concepts are viewed as subcritical fission reactors driven and controlled by high-energy neutrons from a laser-induced fusion reactor. Blanket designs encompassing a substantial portion of the spectrum of different fission reactor technologies are analyzed and compared by calculating their fissile-breeding and fusion-energy-multiplying characteristics. With a large number of different fission technologies to choose from, it is essential to identify more promising hybrid concepts that can then be subjected to in-depth studies that treat the engineering safety, and economic requirements as well as the neutronic aspects. In the course of neutronically analyzing and comparing several fission blanket concepts, this work has demonstrated that fusion-fission hybrids can be designed to meet a broad spectrum of fissile-breeding and fusion-energy-multiplying requirements. The neutronic results should prove to be extremely useful in formulating the technical scope of future studies concerned with evaluating the technical and economic feasibility of hybrid concepts for laser-induced fusion

Recent fusion research in the National Institute for Fusion Science

International Nuclear Information System (INIS)

Komori, Akio; Sakakibara, Satoru; Sagara, Akio; Horiuchi, Ritoku; Yamada, Hiroshi; Takeiri, Yasuhiko

2011-01-01

The National Institute for Fusion Science (NIFS), which was established in 1989, promotes academic approaches toward the exploration of fusion science for steady-state helical reactor and realizes the establishment of a comprehensive understanding of toroidal plasmas as an inter-university research organization and a key center of worldwide fusion research. The Large Helical Device (LHD) Project, the Numerical Simulation Science Project, and the Fusion Engineering Project are organized for early realization of net current free fusion reactor, and their recent activities are described in this paper. The LHD has been producing high-performance plasmas comparable to those of large tokamaks, and several new findings with regard to plasma physics have been obtained. The numerical simulation science project contributes understanding and systemization of the physical mechanisms of plasma confinement in fusion plasmas and explores complexity science of a plasma for realization of the numerical test reactor. In the fusion engineering project, the design of the helical fusion reactor has progressed based on the development of superconducting coils, the blanket, fusion materials and tritium handling. (author)

Three-stage classical molecular dynamics model for simulation of heavy-ion fusion

Directory of Open Access Journals (Sweden)

Godre Subodh S.

2015-01-01

Full Text Available A three-stage Classical Molecular Dynamics (3S-CMD approach for heavy-ion fusion is developed. In this approach the Classical Rigid-Body Dynamics simulation for heavy-ion collision involving light deformed nucleus is initiated on their Rutherford trajectories at very large initial separation. Collision simulation is then followed by relaxation of the rigid-body constrains for one or both the colliding nuclei at distances close to the barrier when the trajectories of all the nucleons are obtained in a Classical Molecular Dynamics approach. This 3S-CMD approach explicitly takes into account not only the long range Coulomb reorientation of the deformed collision partner but also the internal vibrational excitations of one or both the nuclei at distances close to the barrier. The results of the dynamical simulation for 24Mg+208Pb collision show significant modification of the fusion barrier and calculated fusion cross sections due to internal excitations.

Viral membrane fusion

International Nuclear Information System (INIS)

Harrison, Stephen C.

2015-01-01

Membrane fusion is an essential step when enveloped viruses enter cells. Lipid bilayer fusion requires catalysis to overcome a high kinetic barrier; viral fusion proteins are the agents that fulfill this catalytic function. Despite a variety of molecular architectures, these proteins facilitate fusion by essentially the same generic mechanism. Stimulated by a signal associated with arrival at the cell to be infected (e.g., receptor or co-receptor binding, proton binding in an endosome), they undergo a series of conformational changes. A hydrophobic segment (a “fusion loop” or “fusion peptide”) engages the target-cell membrane and collapse of the bridging intermediate thus formed draws the two membranes (virus and cell) together. We know of three structural classes for viral fusion proteins. Structures for both pre- and postfusion conformations of illustrate the beginning and end points of a process that can be probed by single-virion measurements of fusion kinetics. - Highlights: • Viral fusion proteins overcome the high energy barrier to lipid bilayer merger. • Different molecular structures but the same catalytic mechanism. • Review describes properties of three known fusion-protein structural classes. • Single-virion fusion experiments elucidate mechanism

Viral membrane fusion

Energy Technology Data Exchange (ETDEWEB)

Harrison, Stephen C., E-mail: harrison@crystal.harvard.edu

2015-05-15

Membrane fusion is an essential step when enveloped viruses enter cells. Lipid bilayer fusion requires catalysis to overcome a high kinetic barrier; viral fusion proteins are the agents that fulfill this catalytic function. Despite a variety of molecular architectures, these proteins facilitate fusion by essentially the same generic mechanism. Stimulated by a signal associated with arrival at the cell to be infected (e.g., receptor or co-receptor binding, proton binding in an endosome), they undergo a series of conformational changes. A hydrophobic segment (a “fusion loop” or “fusion peptide”) engages the target-cell membrane and collapse of the bridging intermediate thus formed draws the two membranes (virus and cell) together. We know of three structural classes for viral fusion proteins. Structures for both pre- and postfusion conformations of illustrate the beginning and end points of a process that can be probed by single-virion measurements of fusion kinetics. - Highlights: • Viral fusion proteins overcome the high energy barrier to lipid bilayer merger. • Different molecular structures but the same catalytic mechanism. • Review describes properties of three known fusion-protein structural classes. • Single-virion fusion experiments elucidate mechanism.

Hybrid Fusion for Biometrics: Combining Score-level and Decision-level Fusion

NARCIS (Netherlands)

Tao, Q.; Veldhuis, Raymond N.J.

2008-01-01

A general framework of fusion at decision level, which works on ROCs instead of matching scores, is investigated. Under this framework, we further propose a hybrid fusion method, which combines the score-level and decision-level fusions, taking advantage of both fusion modes. The hybrid fusion

Fusion research in the European Community

International Nuclear Information System (INIS)

Wolf, G.H.

1988-01-01

Centering around the European joint project Joint European Torus (JET), in the framework of which hot fusion plasmas are already brought close to thermonuclear ignition, the individual research centres in Europe have taken over different special tasks. In Germany research concentrates above all on the development of super-conductive magnets, the stage of plasma-physical fundamentals or the investigation of the interaction between the plasma boundary layer and the material of the vessel wall. On this basis the development stage following JET, the Next European Torus (NET), is planned, with its main aim being the production and maintenance of a thermonuclear burning plasma, i.e. a plasma which maintains its active state from the gain of energy of its own fusion reactions. In the framework of a contractually agreed cooperation between the European Community, Japan, the USSR and the USA, the establishment of an international study group (with seat in Garching) was decided upon, which is to develop the concept of an 'International Thermonuclear Experimental Reactor (ITER)' jointly supported by these countries. The results of the studies presented show that the differences in the design data of ITER and NET are negligible. (orig./DG) [de

Heat transfer in a two-pass internally ribbed turbine blade coolant channel with cylindrical vortex generators

Energy Technology Data Exchange (ETDEWEB)

Hibbs, R.; Chen, Y.; Nikitopoulos, D. [Louisiana State Univ., Baton Rouge, LA (United States)] [and others

1995-10-01

The effect of vortex generators on the mass (heat) transfer from the ribbed passage of a two pass turbine blade coolant channel is investigated with the intent of optimizing the vortex generator geometry so that significant enhancements in mass/heat transfer can be achieved. In the experimental configuration considered, ribs are mounted on two opposite walls; all four walls along each pass are active and have mass transfer from their surfaces but the ribs are non-participating. Mass transfer measurements, in the form of Sherwood number ratios, are made along the centerline and in selected inter-rib modules. Results are presented for Reynolds number in the range of 5,000 to 40,000, pitch to rib height ratios of 10.5 and 21, and vortex generator-rib spacing to rib height ratios of 0.55, and 1.5. Centerline and spanwise averaged Sherwood number ratios are presented along with contours of the Sherwood number ratios. Results indicate that the vortex generators induce substantial increases in the local mass transfer rates, particularly along the side walls, and modest increases in the average mass transfer rates. The vortex generators have the effect of making the inter-rib profiles along the ribbed walls more uniform. Along the side walls, horse-shoe vortices that characterize the vortex generator wake are associated with significant mass transfer enhancements. The wake effects and the levels of enhancement decrease somewhat with increasing Reynolds number and decreasing pitch.

Controlled nuclear fusion, a challenging task with a big payoff

International Nuclear Information System (INIS)

Noterdaeme, Jean-Marie

2003-01-01

Controlled thermonuclear fusion carries the promise of providing the world with a new source of energy, the same energy that powers the stars. Research in this area has progressed steadily for several decades now, and is ready to move into a new phase. The probability is high that a new international experimental machine (ITER) which will prove the scientific and technological feasibility of fusion energy, will be built. This paper introduces nuclear fusion for people familiar with the fission process. It starts from the basic principles common to fusion and fission. It moves on to point out the differences, explains the reasons for those differences and the consequences. Controlled thermonuclear fusion can be obtained in several ways, which have led to different research lines. One line, on which this talk focuses, is by confining the reacting particles with magnetic fields. Another, which is the subject of a different talk, relies on the inertia of the particles to create the conditions necessary for fusion. The progress of the magnetic confinement research is shown, with examples of major hurdles, which have occurred and have been overcome. Recent results, which make us optimistic that the next machine can prove the feasibility of fusion energy, are highlighted. The talk also addresses the challenges that remain before us, and suggests that the promise of fusion energy opens up new perspectives and opportunities for the development and the use of fission energy. (author)

Peaceful fusion

Energy Technology Data Exchange (ETDEWEB)

Englert, Matthias [IANUS, TU Darmstadt (Germany)

2014-07-01

Like other intense neutron sources fusion reactors have in principle a potential to be used for military purposes. Although the use of fissile material is usually not considered when thinking of fusion reactors (except in fusion-fission hybrid concepts) quantitative estimates about the possible production potential of future commercial fusion reactor concepts show that significant amounts of weapon grade fissile materials could be produced even with very limited amounts of source materials. In this talk detailed burnup calculations with VESTA and MCMATH using an MCNP model of the PPCS-A will be presented. We compare different irradiation positions and the isotopic vectors of the plutonium bred in different blankets of the reactor wall with the liquid lead-lithium alloy replaced by uranium. The technical, regulatory and policy challenges to manage the proliferation risks of fusion power will be addressed as well. Some of these challenges would benefit if addressed at an early stage of the research and development process. Hence, research on fusion reactor safeguards should start as early as possible and accompany the current research on experimental fusion reactors.

International power supply policy and the globalisation of research: the example of fusion research

International Nuclear Information System (INIS)

Bechmann, G.; Gloede, F.; Lessmann, E.

2001-01-01

At the present state of our information, we can affirm that fusion research, as far as the necessary financial expenditures and their political justification are concerned, is a matter of politically controversial debate. In the political arenas, projects like controlled nuclear fusion are discussed primarily with regard to the controllability of complex technical systems and the sustainability of our future supply of electric power. The attempt to discuss this problem will have to consider: (i) on the one hand, already established concepts of sustainability; (ii) and on the other, the - according to the present state of our knowledge - foreseeable characteristics of a system of power generation and supply based on fusion reactors. Not only do the goals of global technology projects have to be embedded in patterns of universally accepted legitimisation (sustainability), but the organisation of research and development is also changing into networks acting globally. In this sense, globalisation means not only the worldwide linking of financial markets and the permanent availability of information and communication networks, but above all the creation of global organisations of research and innovation processes. The globalisation of research and development of technology has several dimensions: (i) the recognition and treatment of global problems; (ii) the transformation and evolution of new forms of organisation and cooperation in a global community of researchers; (iii) the constitution of Global Change Research. Fusion is playing a 'pathfinder role' for these processes and is at the same time itself an expression of the globalisation of the production of technology

Cold fusion, Alchemist's dream

International Nuclear Information System (INIS)

Clayton, E.D.

1989-09-01

In this report the following topics relating to cold fusion are discussed: muon catalysed cold fusion; piezonuclear fusion; sundry explanations pertaining to cold fusion; cosmic ray muon catalysed cold fusion; vibrational mechanisms in excited states of D 2 molecules; barrier penetration probabilities within the hydrogenated metal lattice/piezonuclear fusion; branching ratios of D 2 fusion at low energies; fusion of deuterons into 4 He; secondary D+T fusion within the hydrogenated metal lattice; 3 He to 4 He ratio within the metal lattice; shock induced fusion; and anomalously high isotopic ratios of 3 He/ 4 He

Progress of nuclear fusion research and review on development of fusion reactors

International Nuclear Information System (INIS)

1976-01-01

Set up in October 1971, the ad hoc Committee on Survey of Nuclear Fusion Reactors has worked on overall fusion reactor aspects and definition of the future problems under four working groups of core, nuclear heat, materials and system. The presect volume is intended to provide reference materials in the field of fusion reactor engineering, prepared by members of the committee. Contents are broadly the following: concept of the nuclear fusion reactor, fusion core engineering, fusion reactor blanket engineering, fusion reactor materials engineering, and system problems in development of fusion reactors. (Mori, K.)

Plasma physics for controlled fusion. 2. ed.

Energy Technology Data Exchange (ETDEWEB)

Miyamoto, Kenro

2016-08-01

This new edition presents the essential theoretical and analytical methods needed to understand the recent fusion research of tokamak and alternate approaches. The author describes magnetohydrodynamic and kinetic theories of cold and hot plasmas in detail. The book covers new important topics for fusion studies such as plasma transport by drift turbulence, which depend on the magnetic configuration and zonal flows. These are universal phenomena of microturbulence. They can modify the onset criterion for turbulent transport, instabilities driven by energetic particles as well as alpha particle generation and typical plasma models for computer simulation. The fusion research of tokamaks with various new versions of H modes are explained. The design concept of ITER, the international tokamak experimental reactor, is described for inductively driven operations as well as steady-state operations using non-inductive drives. Alternative approaches of reversed-field pinch and its relaxation process, stellator including quasi-symmetric system, open-end system of tandem mirror and inertial confinement are also explained. Newly added and updated topics in this second edition include zonal flows, various versions of H modes, and steady-state operations of tokamak, the design concept of ITER, the relaxation process of RFP, quasi-symmetric stellator, and tandem mirror. The book addresses graduate students and researchers in the field of controlled fusion.

Plasma physics for controlled fusion. 2. ed.

International Nuclear Information System (INIS)

Miyamoto, Kenro

2016-01-01

This new edition presents the essential theoretical and analytical methods needed to understand the recent fusion research of tokamak and alternate approaches. The author describes magnetohydrodynamic and kinetic theories of cold and hot plasmas in detail. The book covers new important topics for fusion studies such as plasma transport by drift turbulence, which depend on the magnetic configuration and zonal flows. These are universal phenomena of microturbulence. They can modify the onset criterion for turbulent transport, instabilities driven by energetic particles as well as alpha particle generation and typical plasma models for computer simulation. The fusion research of tokamaks with various new versions of H modes are explained. The design concept of ITER, the international tokamak experimental reactor, is described for inductively driven operations as well as steady-state operations using non-inductive drives. Alternative approaches of reversed-field pinch and its relaxation process, stellator including quasi-symmetric system, open-end system of tandem mirror and inertial confinement are also explained. Newly added and updated topics in this second edition include zonal flows, various versions of H modes, and steady-state operations of tokamak, the design concept of ITER, the relaxation process of RFP, quasi-symmetric stellator, and tandem mirror. The book addresses graduate students and researchers in the field of controlled fusion.

Fusion power: the transition from fundamental science to fusion reactor engineering

International Nuclear Information System (INIS)

Post, R.F.

1975-01-01

The historical development of fusion research is outlined. The basics of fusion power along with fuel cost and advantages of fusion are discussed. Some quantitative requirements for fusion power are described. (MOW)

Fusion Canada

International Nuclear Information System (INIS)

1987-07-01

This first issue of a quarterly newsletter announces the startup of the Tokamak de Varennes, describes Canada's national fusion program, and outlines the Canadian Fusion Fuels Technology Program. A map gives the location of the eleven principal fusion centres in Canada. (L.L.)

Snowmass 2002: The Fusion Energy Sciences Summer Study; TOPICAL

International Nuclear Information System (INIS)

N. Sauthoff; G. Navratil; R. Bangerter

2002-01-01

The Fusion Summer Study 2002 will be a forum for the critical technical assessment of major next-steps in the fusion energy sciences program, and will provide crucial community input to the long-range planning activities undertaken by the DOE[Department of Energy] and the FESAC[Fusion Energy Sciences Advisory Committee]. It will be an ideal place for a broad community of scientists to examine goals and proposed initiatives in burning plasma science in magnetic fusion energy and integrated research experiments in inertial fusion energy. This meeting is open to every member of the fusion energy science community and significant international participation is encouraged. The objectives of the Fusion Summer Study are three: (1) Review scientific issues in burning plasmas to establish the basis for the following two objectives and to address the relations of burning plasma in tokamaks to innovative magnetic fusion energy (MFE) confinement concepts and of ignition in inertial fusion energy (IFE) to integrated research facilities. (2) Provide a forum for critical discussion and review of proposed MFE burning plasma experiments (e.g., IGNITOR, FIRE, and ITER) and assess the scientific and technological research opportunities and prospective benefits of these approaches to the study of burning plasmas. (3) Provide a forum for the IFE community to present plans for prospective integrated research facilities, assess present status of the technical base for each, and establish a timetable and technical progress necessary to proceed for each. Based on significant preparatory work by the fusion community prior to the July Snowmass meeting, the Snowmass working groups will prepare a draft report that documents the scientific and technological benefits of studies of burning plasmas. The report will also include criteria by which the benefits of each approach to fusion science, fusion engineering/technology, and the fusion development path can be assessed. Finally, the report will

Impact of fluorescent protein fusions on the bacterial flagellar motor.

Science.gov (United States)

Heo, M; Nord, A L; Chamousset, D; van Rijn, E; Beaumont, H J E; Pedaci, F

2017-10-03

Fluorescent fusion proteins open a direct and unique window onto protein function. However, they also introduce the risk of perturbation of the function of the native protein. Successful applications of fluorescent fusions therefore rely on a careful assessment and minimization of the side effects, but such insight is still lacking for many applications. This is particularly relevant in the study of the internal dynamics of motor proteins, where both the chemical and mechanical reaction coordinates can be affected. Fluorescent proteins fused to the stator of the Bacterial Flagellar Motor (BFM) have previously been used to unveil the motor subunit dynamics. Here we report the effects on single motors of three fluorescent proteins fused to the stators, all of which altered BFM behavior. The torque generated by individual stators was reduced while their stoichiometry remained unaffected. MotB fusions decreased the switching frequency and induced a novel bias-dependent asymmetry in the speed in the two directions. These effects could be mitigated by inserting a linker at the fusion point. These findings provide a quantitative account of the effects of fluorescent fusions to the stator on BFM dynamics and their alleviation- new insights that advance the use of fluorescent fusions to probe the dynamics of protein complexes.

Atomic fusion, Gerrard atomic fusion

International Nuclear Information System (INIS)

Gerrard, T.H.

1980-01-01

In the approach to atomic fusion described here the heat produced in a fusion reaction, which is induced in a chamber by the interaction of laser beams and U.H.F. electromagnetic beams with atom streams, is transferred to a heat exchanger for electricity generation by a coolant flowing through a jacket surrounding the chamber. (U.K.)

Hybrid Image Fusion for Sharpness Enhancement of Multi-Spectral Lunar Images

Science.gov (United States)

Awumah, Anna; Mahanti, Prasun; Robinson, Mark

2016-10-01

Image fusion enhances the sharpness of a multi-spectral (MS) image by incorporating spatial details from a higher-resolution panchromatic (Pan) image [1,2]. Known applications of image fusion for planetary images are rare, although image fusion is well-known for its applications to Earth-based remote sensing. In a recent work [3], six different image fusion algorithms were implemented and their performances were verified with images from the Lunar Reconnaissance Orbiter (LRO) Camera. The image fusion procedure obtained a high-resolution multi-spectral (HRMS) product from the LRO Narrow Angle Camera (used as Pan) and LRO Wide Angle Camera (used as MS) images. The results showed that the Intensity-Hue-Saturation (IHS) algorithm results in a high-spatial quality product while the Wavelet-based image fusion algorithm best preserves spectral quality among all the algorithms. In this work we show the results of a hybrid IHS-Wavelet image fusion algorithm when applied to LROC MS images. The hybrid method provides the best HRMS product - both in terms of spatial resolution and preservation of spectral details. Results from hybrid image fusion can enable new science and increase the science return from existing LROC images.[1] Pohl, Cle, and John L. Van Genderen. "Review article multisensor image fusion in remote sensing: concepts, methods and applications." International journal of remote sensing 19.5 (1998): 823-854.[2] Zhang, Yun. "Understanding image fusion." Photogramm. Eng. Remote Sens 70.6 (2004): 657-661.[3] Mahanti, Prasun et al. "Enhancement of spatial resolution of the LROC Wide Angle Camera images." Archives, XXIII ISPRS Congress Archives (2016).