Personnel Safety for Future Magnetic Fusion Power Plants

International Nuclear Information System (INIS)

Cadwallader, Lee

2009-01-01

The safety of personnel at existing fusion experiments is an important concern that requires diligence. Looking to the future, fusion experiments will continue to increase in power and operating time until steady state power plants are achieved; this causes increased concern for personnel safety. This paper addresses four important aspects of personnel safety in the present and extrapolates these aspects to future power plants. The four aspects are personnel exposure to ionizing radiation, chemicals, magnetic fields, and radiofrequency (RF) energy. Ionizing radiation safety is treated well for present and near-term experiments by the use of proven techniques from other nuclear endeavors. There is documentation that suggests decreasing the annual ionizing radiation exposure limits that have remained constant for several decades. Many chemicals are used in fusion research, for parts cleaning, as use as coolants, cooling water cleanliness control, lubrication, and other needs. In present fusion experiments, a typical chemical laboratory safety program, such as those instituted in most industrialized countries, is effective in protecting personnel from chemical exposures. As fusion facilities grow in complexity, the chemical safety program must transition from a laboratory scale to an industrial scale program that addresses chemical use in larger quantity. It is also noted that allowable chemical exposure concentrations for workers have decreased over time and, in some cases, now pose more stringent exposure limits than those for ionizing radiation. Allowable chemical exposure concentrations have been the fastest changing occupational exposure values in the last thirty years. The trend of more restrictive chemical exposure regulations is expected to continue into the future. Other issues of safety importance are magnetic field exposure and RF energy exposure. Magnetic field exposure limits are consensus values adopted as best practices for worker safety; a typical

Stat-of-the art of nuclear fusion and its future outlook in

International Nuclear Information System (INIS)

Abdelaziz, M.E.; Elnadi, A.M.; Masoud, M.; Elshaer, M.A.; Khalil, S.M.

1993-01-01

The study in this project is carried out with the objective of being able to present a clear view for the state-of-the art of nuclear fusion as one of the most promising coming energy source and its future outlook in Egypt. The study introduce a summary of the world energy problem and the advantages of thermonuclear fusion energy compared to other energy sources. A description of the two main techniques of confining plasma in the fusion experiments, namely the magnetic and the inertial confinement. These techniques are discussed and investigated through linear pinches and tokamaks. Tokamaks showed to be a promising machines for achieving the controlled thermonuclear fusion power reactor. Recent development of the research on laser fusion together with fast progress in pellet and laser technology suggest that it may be possible to achieve laser fusion power reactor. The story of the strange phenomena of cold fusion, muon-catalyzed fusion, and cold fusion in condensed matter are also studied and showed to be non promising. The project study in details the future fusion reactor, its nuclear engineering and its safety and environmental aspects. The study is based on the magnetic fusion using the tokamak configuration. The positive safety and environmental aspects of fusion reactors, if exist, is also investigated. Status of plasma physics and nuclear fusion activities and strategies in the developing countries (including egypt and the arab countries) are reviewed, besides, some national programmes are proposed. In addition, the status of international activities in plasma technology and its application are represented. Future outlook for egyptian programmes on different plasma technologies are studied. Finally, conclusions and recommendations are presented which summarized the principle achiements and future research opportunities in nuclear fusion activities. In fact, it must be emphasized that fusion is an exciting and challenging field of research -the most

Economic and environmental performance of future fusion plants in comparison

International Nuclear Information System (INIS)

Hamacher, T.; Saez, R.M.; Lako, P.

2001-01-01

If the good performance of fusion as technology with no CO 2 emission during normal operation and rather low external costs, reflecting the advantageous environmental and safety characteristics, are considered in future energy regulations, fusion can win considerable market shares in future electricity markets. The economic performance was elaborated for Western Europe for the time period till 2100. The software tool MARKAL widely used in energy research was used to simulate and optimise the development of the Western European energy system. Two different scenarios were considered, the main difference was the interest rate for investments. Stringent CO 2 -emission strategies lead to considerable market shares for fusion. As a comprehensive indicator of the environmental and safety performance of fusion plants the external costs following the ExternE method was used. External costs of fusion are rather low, much below the cost of electricity, and are in the same range as photovoltaics and wind energy. (author)

Intelligible seminar on fusion reactors. (12) Next step toward the realization of fusion reactors. Future vision of fusion energy research and development

International Nuclear Information System (INIS)

Okano, Kunihiko; Kurihara, Kenichi; Tobita, Kenji

2006-01-01

In the last session of this seminar the progress of research and development for the realization of fusion reactors and future vision of fusion energy research and development are summarized. The some problems to be solved when the commercial fusion reactors would be realized, (1) production of deuterium as the fuel, (2) why need the thermonuclear reactors, (3) environmental problems, and (4) ITER project, are described. (H. Mase)

Fusion Power: A Strategic Choice for the Future Energy Provision. Why is So Much Time Wasted for Decision Making?

International Nuclear Information System (INIS)

D'haeseleer, William D.

2005-01-01

From a general analysis of the world energy issue, it is argued that an affordable, clean and reliable energy supply will have to consist of a portfolio of primary energy sources, a large fraction of which will be converted to a secondary carrier in large baseload plants. Because of all future uncertainties, it would be irresponsible not to include thermonuclear fusion as one of the future possibilities for electricity generation.The author tries to understand why nuclear-fusion research is not considered of strategic importance by the major world powers. The fusion programs of the USA and Europe are taken as prime examples to illustrate the 'hesitation'. Europe is now advocating a socalled 'fast-track' approach, thereby seemingly abandoning the 'classic' time frame towards fusion that it has projected for many years. The US 'oscillatory' attitude towards ITER in relation to its domestic program is a second case study that is looked at.From the real history of the ITER design and the 'siting' issue, one can try to understand how important fusion is considered by these world powers. Not words are important, but deeds. Fast tracks are nice to talk about, but timely decisions need to be taken and sufficient money is to be provided. More fundamental understanding of fusion plasma physics is important, but in the end, real hardware devices must be constructed to move along the path of power plant implementation.The author tries to make a balance of where fusion power research is at this moment, and where, according to his views, it should be going

Introducing the book 'Cold fusion and the future'

International Nuclear Information System (INIS)

Rothwell, Jed

2006-01-01

Cold fusion will be the ideal source of energy, provided its introduction can be handled properly. A few cells have shown power density and temperatures suitable for real-world applications. Once these cells can be replicated on demand, commercial development will be straightforward. Manufacturing should not be too demanding, so thousands of companies will compete, and costs will fall quickly. The transition from fossil fuel to cold fusion will be rapid. Many extraordinary new applications will become possible, and seemingly intractable problems such as global warming may be fixed. Some examples will be presented. Public support is essential to funding research, and commercialization. 'Cold Fusion and the Future' is the title of a new book by this author. This paper discusses a few of the topics in the book

Use of high temperature superconductors for future fusion magnet systems

Energy Technology Data Exchange (ETDEWEB)

Fietz, W H [Forschungszentrum Karlsruhe, Institut fuer Technische Physik, Karlsruhe (Germany); Celentano, G; Della Corte, A [Superconductivity Division, ENEA - Frascati Research Center, Frascati (Italy); Goldacker, W; Heller, R; Komarek, P; Kotzyba, G; Nast, R; Obst, B; Schlachter, S I; Schmidt, C; Zahn, G [Forschungszentrum Karlsruhe, Institut fuer Technische Physik, Karlsruhe (Germany); Pasztor, G; Wesche, R [Centre de Recherches en Physique des Plasmas, Villingen (Switzerland); Salpietro, E; Vostner, A [European Fusion Development Agreement, Close Support Unit, Garching (Germany)

2005-01-01

With the construction of ITER the feasibility of a fusion machine will be demonstrated. To commercialize fusion it is essential to keep losses as small as possible in future fusion power plants. One major component where losses can be strongly reduced is the cooling system. For example in ITER where efficiency is not a major goal, a cooling power of 64 kW at 4.4 K is foreseen taking more than 20 MW electric power. Considering the size of future commercial fusion machines this consumption of electric power for cooling will even be higher. With a magnet system working at 20 K a fusion machine would work more efficient by a factor of 5-10 with respect to electric power consumption for cryogenics. Even better than that, would be a machine with a magnet system operating at 65 K to 77 K. In this case liquid nitrogen could be used as coolant saving money for investment and operation costs. Such an increase in the operating temperature of the magnet system can be achieved by the use of High- Temperature Superconductors (HTS). In addition the use of HTS would allow much smaller efforts for thermal shielding and alternative thermal insulation concepts may be possible, e.g. for an HTS bus bar system. This contribution will give an overview about status, promises and challenges of HTS conductors on the way to an HTS fusion magnet system beyond ITER. (author)

Recent Accomplishments and Future Directions in US Fusion Safety & Environmental Program

Energy Technology Data Exchange (ETDEWEB)

David A. Petti; Brad J. Merrill; Phillip Sharpe; L. C. Cadwallader; L. El-Guebaly; S. Reyes

2006-07-01

The US fusion program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behavior of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state of the art S&E computer codes and risk tools for safety assessment, and evaluating S&E issues associated with current fusion designs. In this paper, recent accomplishments are reviewed and future directions outlined.

Progress of research and development of nuclear fusion and development of large nuclear fusion device technology

International Nuclear Information System (INIS)

1994-01-01

In the last several years, the results of tokamak experiments were conspicuous, and the progress of plasma confinement performance, transport mechanism, divertors and impurities, helium transport and exhaust, electric current drive, magnetic field ripple effect and high speed particle transport and DT experiment are reported. The other confinement methods than tokamak, the related theories and reactor technology are described. The conceptual design of ITER was carried out by the cooperation of Japan, USA, EC and the former USSR. The projects of developing nuclear fusion in various countries, the design and the required research and development of ITER, the reconstruction and the required research and development of JT-60, JET and TFTR, the design and the required research and development of large helical device, the state of research and development of laser nuclear fusion and inversion magnetic field pinch nuclear fusion, the activities and roles of industrial circles in large nuclear fusion device technology, and the long term perspective of the technical development of nuclear fusion are described. (K.I.)

Economic viability of large-scale fusion systems

Energy Technology Data Exchange (ETDEWEB)

Helsley, Charles E., E-mail: cehelsley@fusionpowercorporation.com; Burke, Robert J.

2014-01-01

A typical modern power generation facility has a capacity of about 1 GWe (Gigawatt electric) per unit. This works well for fossil fuel plants and for most fission facilities for it is large enough to support the sophisticated generation infrastructure but still small enough to be accommodated by most utility grid systems. The size of potential fusion power systems may demand a different viewpoint. The compression and heating of the fusion fuel for ignition requires a large driver, even if it is necessary for only a few microseconds or nanoseconds per energy pulse. The economics of large systems, that can effectively use more of the driver capacity, need to be examined. The assumptions used in this model are specific for the Fusion Power Corporation (FPC) SPRFD process but could be generalized for any system. We assume that the accelerator is the most expensive element of the facility and estimate its cost to be $20 billion. Ignition chambers and fuel handling facilities are projected to cost $1.5 billion each with up to 10 to be serviced by one accelerator. At first this seems expensive but that impression has to be tempered by the energy output that is equal to 35 conventional nuclear plants. This means the cost per kWh is actually low. Using the above assumptions and industry data for generators and heat exchange systems, we conclude that a fully utilized fusion system will produce marketable energy at roughly one half the cost of our current means of generating an equivalent amount of energy from conventional fossil fuel and/or fission systems. Even fractionally utilized systems, i.e. systems used at 25% of capacity, can be cost effective in many cases. In conclusion, SPRFD systems can be scaled to a size and configuration that can be economically viable and very competitive in today's energy market. Electricity will be a significant element in the product mix but synthetic fuels and water may also need to be incorporated to make the large system

Economic viability of large-scale fusion systems

International Nuclear Information System (INIS)

Helsley, Charles E.; Burke, Robert J.

2014-01-01

A typical modern power generation facility has a capacity of about 1 GWe (Gigawatt electric) per unit. This works well for fossil fuel plants and for most fission facilities for it is large enough to support the sophisticated generation infrastructure but still small enough to be accommodated by most utility grid systems. The size of potential fusion power systems may demand a different viewpoint. The compression and heating of the fusion fuel for ignition requires a large driver, even if it is necessary for only a few microseconds or nanoseconds per energy pulse. The economics of large systems, that can effectively use more of the driver capacity, need to be examined. The assumptions used in this model are specific for the Fusion Power Corporation (FPC) SPRFD process but could be generalized for any system. We assume that the accelerator is the most expensive element of the facility and estimate its cost to be $20 billion. Ignition chambers and fuel handling facilities are projected to cost $1.5 billion each with up to 10 to be serviced by one accelerator. At first this seems expensive but that impression has to be tempered by the energy output that is equal to 35 conventional nuclear plants. This means the cost per kWh is actually low. Using the above assumptions and industry data for generators and heat exchange systems, we conclude that a fully utilized fusion system will produce marketable energy at roughly one half the cost of our current means of generating an equivalent amount of energy from conventional fossil fuel and/or fission systems. Even fractionally utilized systems, i.e. systems used at 25% of capacity, can be cost effective in many cases. In conclusion, SPRFD systems can be scaled to a size and configuration that can be economically viable and very competitive in today's energy market. Electricity will be a significant element in the product mix but synthetic fuels and water may also need to be incorporated to make the large system economically

On interaction of large dust grains with fusion plasma

International Nuclear Information System (INIS)

Krasheninnikov, S. I.; Smirnov, R. D.

2009-01-01

So far the models used to study dust grain-plasma interactions in fusion plasmas neglect the effects of dust material vapor, which is always present around dust in rather hot and dense edge plasma environment in fusion devices. However, when the vapor density and/or the amount of ionized vapor atoms become large enough, they can alter the grain-plasma interactions. Somewhat similar processes occur during pellet injection in fusion plasma. In this brief communication the applicability limits of the models ignoring vapor effects in grain-plasma interactions are obtained.

Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices

NARCIS (Netherlands)

Philipps, V.; Malaquias, A.; Hakola, A.; Karhunen, J.; Maddaluno, G.; Almaviva, S.; Caneve, L.; Colao, F.; Fortuna, E.; Gasior, P.; Kubkowska, M.; Czarnecka, A.; Laan, M.; Lissovski, A.; Paris, P.; van der Meiden, H. J.; Petersson, P.; Rubel, M.; Huber, A.; Zlobinski, M.; Schweer, B.; Gierse, N.; Xiao, Q.; Sergienko, G.

2013-01-01

Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the

Industry perspectives on future directions in the fusion program

International Nuclear Information System (INIS)

Maniscalco, J.A.; Bell, J.M.

1985-01-01

Industry is the ultimate recipient of the product of the fusion development program. However, budget trends are causing the program to lose it's focus on the energy goal, thus diminishing opportunities for a meaningful industrial role at a time when technical progress has been remarkable and scientific feasibility is being demonstrated. The findings of the Magnetic Fusion Advisory Committee Panel charged to report on industrial participation in fusion energy development are summarized. A recommendation of this panel was to increase intellectual involvement of industry in the development of fusion. Opportunities to achieve this include forming partnerships with national laboratories and universities, assigning industry responsibility for a complete scope of work, and assigning industry a major role in system studies and reactor design. These opportunities can be implemented without requiring large budget increases. Increasing the involvement of industry in the fusion program will provide both long and short-term benefits

HFR irradiation testing of fusion materials

International Nuclear Information System (INIS)

Conrad, R.; von der Hardt, P.; Loelgen, R.; Scheurer, H.; Zeisser, P.

1984-01-01

The present and future role of the High Flux Reactor Petten for fusion materials testing has been assessed. For practical purposes the Tokamak-based fusion reactor is chosen as a point of departure to identify material problems and materials data needs. The identification is largely based on the INTOR and NET design studies, the reported programme strategies of Japan, the U.S.A. and the European Communities for technical development of thermonuclear fusion reactors and on interviews with several experts. Existing and planned irradiation facilities, their capabilities and limitations concerning materials testing have been surveyed and discussed. It is concluded that fission reactors can supply important contributions for fusion materials testing. From the point of view of future availability of fission testing reactors and their performance it appears that the HFR is a useful tool for materials testing for a large variety of materials. Prospects and recommendations for future developments are given

An Assessment of the Economics of Future Electric Power Generation Options and the Implications for Fusion

International Nuclear Information System (INIS)

Delene, Jerry G.; Sheffield, John; Williams, Kent A.; Reid, R. Lowell; Hadley, Stan

2001-01-01

This study examines the potential range of electric power costs for some major alternatives to fusion electric power generation when it is ultimately deployed in the middle of the 21st century and, thus, offers a perspective on the cost levels that fusion must achieve to be competitive. The alternative technologies include coal burning, coal gasification, natural gas, nuclear fission, and renewable energy. The cost of electricity (COE) from the alternatives to fusion should be in a 30 to 53 mills/kW.h (1999 dollars) range if carbon sequestration is not needed, 30 to 61 mills/kW.h if sequestration is required, or as high as 83 mills/kW.h for the worst-case scenario for cost uncertainty. The reference COE range for fusion was estimated at 65 to 102 mills/kW.h for 1- to 1.3-GW(electric) scale power plants, based on the tokamak concept. Tokamak fusion costs will have to be reduced and/or cost-effective alternative nontokamak concepts devised before fusion will be competitive with the alternatives for the future production of electricity. Fortunately, there are routes to achieve this goal. Recent results from fusion experiments and developments in technology and engineering solutions indicate that lower cost fusion power plants are possible at the 1-GW(electric) level. Another general route for fusion to reduce costs is to go to large plant sizes [multigigawatts (electric)

The future of fusion

International Nuclear Information System (INIS)

Sheffield, John

2001-01-01

interesting approach is to use the power plant to co-produce electricity and hydrogen to facilitate the introduction of lower cost of electricity, multi-gigawatt power plants (Sheffield et al., A study of options for the deployment of large fusion power plants, 2000, to be published)

Fusion-fission dynamics and perspectives of future experiments

International Nuclear Information System (INIS)

Zagrebaev, V.I.; Itkis, M.G.; Oganessian, Yu.Ts.

2003-01-01

The paper is focused on reaction dynamics of superheavy-nucleus formation and decay at beam energies near the Coulomb barrier. The aim is to review the things we have learned from recent experiments on fusion-fission reactions leading to the formation of compound nuclei with Z ≥ 102 and from their extensive theoretical analysis. Major attention is paid to the dynamics of formation of very heavy compound nuclei taking place in strong competition with the process of fast fission (quasifission). The choice of collective degrees of freedom playing a fundamental role and finding the multidimensional driving potential and the corresponding dynamic equation regulating the whole process are discussed. A possibility of deriving the fission barriers of superheavy nuclei directly from performed experiments is of particular interest here. In conclusion, the results of a detailed theoretical analysis of available experimental data on the 'cold' and 'hot' fusion-fission reactions are presented. Perspectives of future experiments are discussed along with additional theoretical studies in this field needed for deeper understanding of the fusion-fission processes of very heavy nuclear systems

New design of cable-in-conduit conductor for application in future fusion reactors

Science.gov (United States)

Qin, Jinggang; Wu, Yu; Li, Jiangang; Liu, Fang; Dai, Chao; Shi, Yi; Liu, Huajun; Mao, Zhehua; Nijhuis, Arend; Zhou, Chao; Yagotintsev, Konstantin A.; Lubkemann, Ruben; Anvar, V. A.; Devred, Arnaud

2017-11-01

The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device whose magnet system includes toroidal field, central solenoid (CS) and poloidal field coils. The main goal is to build a fusion engineering tokamak reactor with about 1 GW fusion power and self-sufficiency by blanket. In order to reach this high performance, the magnet field target is 15 T. However, the huge electromagnetic load caused by high field and current is a threat for conductor degradation under cycling. The conductor with a short-twist-pitch (STP) design has large stiffness, which enables a significant performance improvement in view of load and thermal cycling. But the conductor with STP design has a remarkable disadvantage: it can easily cause severe strand indentation during cabling. The indentation can reduce the strand performance, especially under high load cycling. In order to overcome this disadvantage, a new design is proposed. The main characteristic of this new design is an updated layout in the triplet. The triplet is made of two Nb3Sn strands and one soft copper strand. The twist pitch of the two Nb3Sn strands is large and cabled first. The copper strand is then wound around the two superconducting strands (CWS) with a shorter twist pitch. The following cable stages layout and twist pitches are similar to the ITER CS conductor with STP design. One short conductor sample with a similar scale to the ITER CS was manufactured and tested with the Twente Cable Press to investigate the mechanical properties, AC loss and internal inspection by destructive examination. The results are compared to the STP conductor (ITER CS and CFETR CSMC) tests. The results show that the new conductor design has similar stiffness, but much lower strand indentation than the STP design. The new design shows potential for application in future fusion reactors.

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

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

Introducing the book 'Cold fusion and the future'

Energy Technology Data Exchange (ETDEWEB)

Rothwell, Jed

2006-07-01

Cold fusion will be the ideal source of energy, provided its introduction can be handled properly. A few cells have shown power density and temperatures suitable for real-world applications. Once these cells can be replicated on demand, commercial development will be straightforward. Manufacturing should not be too demanding, so thousands of companies will compete, and costs will fall quickly. The transition from fossil fuel to cold fusion will be rapid. Many extraordinary new applications will become possible, and seemingly intractable problems such as global warming may be fixed. Some examples will be presented. Public support is essential to funding research, and commercialization. 'Cold Fusion and the Future' is the title of a new book by this author. This paper discusses a few of the topics in the book.

The contribution of fusion to sustainable development

International Nuclear Information System (INIS)

Ward, D.J.

2007-01-01

The world demand for energy is projected to more than double over the next 50 years, indeed this will be essential to bring much of the world out of poverty. At the same time there is increasing pressure to substantially reduce atmospheric pollution, most notably of carbon dioxide. Together, these conflicting goals drive a need to produce enormous amounts of non-carbon energy supply, much greater than our total present energy supply. This presents a huge challenge. As one of very few options for large-scale, non-carbon future supply of energy, fusion has the potential to make an important contribution to sustained energy supplies. Fusion's advantages of large fuel reserves, low atmospheric emissions and high levels of safety make it an important consideration in future energy strategies. Conceptual designs of fusion power plants have been optimised against safety and environmental criteria; the results are described here and the outcomes compared with other energy sources. To make a contribution to sustainable development, fusion must be economically viable in a future energy market. The calculated costs of electricity from fusion show that, particularly in an energy market where environmental constraints are playing an increasing role, fusion can make an important contribution

Limitation of fusion power plant installation on future power grids under the effect of renewable and nuclear power sources

Energy Technology Data Exchange (ETDEWEB)

Takeda, Shutaro, E-mail: takeda.shutarou.55r@st.kyoto-u.ac.jp [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Sakurai, Shigeki [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Yamamoto, Yasushi [Faculty of Engineering Science, Kansai University, Suita, Osaka (Japan); Kasada, Ryuta; Konishi, Satoshi [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan)

2016-11-01

Graphical abstract: - Highlights: • Future power grids would be unstable due to renewable and nuclear power sources. • Output interruptions of fusion plant would cause disturbances to future grids. • Simulation results suggested they would create limitations in fusion installation. • A novel diagram was presented to illustrate this suggested limitation. - Abstract: Future power grids would be unstable because of the larger share of renewable and nuclear power sources. This instability might bring some additional difficulties to fusion plant installation. Therefore, the authors carried out a quantitative feasibility study from the aspect of grid stability through simulation. Results showed that the more renewable and nuclear sources are linked to a grid, the greater disturbance the grid experiences upon a sudden output interruption of a fusion power plant, e.g. plasma disruption. The frequency deviations surpassed 0.2 Hz on some grids, suggesting potential limitations of fusion plant installation on future grids. To clearly show the suggested limitations of fusion plant installations, a novel diagram was presented.

The economic viability of fusion power

International Nuclear Information System (INIS)

Ward, D.J.; Cook, I.; Lechon, Y.; Saez, R.

2005-01-01

Although fusion power is being developed because of its large resource base, low environmental impact and high levels of intrinsic safety, it is important to investigate the economics of a future fusion power plant to check that the electricity produced can, in fact, have a market. The direct cost of electricity of a fusion power plant and its key dependencies on the physics and technology assumptions, are calculated, as are the materials requirements. The other important aspect of costs, the external costs which can arise from effects such as pollution, accidents and waste are also given. Fusion is found to offer the prospect of a new energy source with acceptable direct costs and very low external costs. This places fusion in a strong position in a future energy market, especially one in which environmental constraints become increasingly important

Fusion power in a future low carbon global electricity system

DEFF Research Database (Denmark)

Cabal, H.; Lechón, Y.; Bustreo, C.

2017-01-01

Fusion is one of the technologies that may contribute to a future, low carbon, global energy supply system. In this article we investigate the role that it may play under different scenarios. The global energy model ETM (originally EFDA TIMES Model) has been used to analyse the participation...

Divertor development for a future fusion power plant

International Nuclear Information System (INIS)

Norajitra, Prachai

2011-01-01

Nuclear fusion is considered as a future source of sustainable energy supply. In the first chapter, the physical principle of magnetic plasma confinement, and the function of a tokamak are described. Since the discovery of the H-mode in ASDEX experiment ''Divertor I'' in 1982, the divertor has been an integral part of all modern tokamaks and stellarators, not least the ITER machine. The goal of this work is to develop a feasible divertor design for a fusion power plant to be built after ITER. This task is particularly challenging because a fusion power plant formulates much greater demands on the structural material and the design than ITER in terms of neutron wall load and radiation. First several divertor concepts proposed in the literature e.g. the Power Plant Conceptual Study (PPCS) using different coolants are reviewed and analyzed with respect to their performance. As a result helium cooled divertor concept exhibited the best potential to come up to the highest safety requirements and therefore has been chosen for the design process. From the third chapter the necessary steps towards this goal are described. First, the boundary conditions for the arrangement of a divertor with respect to the fusion plasma are discussed, as this determines the main thermal and neutronic load parameters. Based on the loads material selection criteria are inherently formulated. In the next step, the reference design is defined in accordance with the established functional design specifications. The developed concept is of modular nature and consists of cooling fingers of tungsten using an impingement cooling in order to achieve a heat dissipation of 10 MW/m 2 . In the next step, the design was subjected to the thermal-hydraulic and thermo-mechanical calculations in order to analyze and improve the performance and the manufacturing technologies. Based on these results, a prototype was produced and experimentally tested on their cooling capacity, their thermo-cyclic loading

Institute for Fusion Research and Large Helical Device program

International Nuclear Information System (INIS)

Iiyoshi, Atsuo

1989-01-01

In the research on nuclear fusion, the final objective is to materialize nuclear fusion reactors, and for the purpose, it is necessary to cause nuclear combustion by making the plasma of higher than 100 million deg and confine it for a certain time. So far in various universities, the researches on diversified fusion processes have been advanced, but in February, 1986, the Science Council issued the report 'Nuclear fusion research in universities hereafter'. As the next large scale device, an external conductor system helical device was decided, and it is desirable to found the organization for joint utilization by national universities to promote the project. The researches on the other processes are continued by utilizing the existing facilitie. The reason of selecting a helical device is the data base of the researches carried out so far can be utilized sufficiently, it is sufficiently novel even after 10 years from now, and many researchers can be collected. The place of the research is Toki City, Gifu Prefecture, where the Institute of Plasma Physics, Nagoya University, is to be moved. The basic concept of the superconducting helical device project, the trend of nuclear fusion development in the world, the physical research using a helical system and so on are reported. (Kako, I.)

Revised assessments of the economics of fusion power

International Nuclear Information System (INIS)

Han, W.E.; Ward, D.J.

2009-01-01

Although fusion power is being developed because of its large resource base, low environmental impact and high levels of intrinsic safety, it is also important to investigate the economics of a future fusion power plant in order to assess the potential market for the electricity produced. As part of the PPCS (Power Plant Conceptual Study) in Europe, published in 2005, an assessment was made of the likely economic performance of the range of fusion power plant concepts studied. Since that time, new work has been carried out, within the fusion programme, and particularly in the EU DEMO study, that changes a number of the important assumptions made in the PPCS. These changes allow either reduced cost versions of the PPCS plant models or, alternatively, plants with less ambitious technical assumptions at constant cost. The impact of the new results, emerging from the EU DEMO studies, on the role of fusion in the future energy market is described. A new energy economics model is employed to analyse the potential market performance of fusion power in a range of future energy scenarios and this shows that there can be a significant role for fusion in a future energy market.

Fusion reactors as a future energy source

International Nuclear Information System (INIS)

Seifritz, W.

A detailed update of fusion research concepts is given. Discussions are given for the following areas: (1) the magnetic confinement principle, (2) UWMAK I: conceptual design for a fusion reactor, (3) the inertial confinement principle, (4) the laser fusion power plant, (5) electron-induced fusion, (6) the long-term development potential of fusion reactors, (7) the symbiosis between fusion and fission reactors, (8) fuel supply for fusion reactors, (9) safety and environmental impact, and (10) accidents, and (11) waste removal and storage

Criteria for the assessment of fusion power

International Nuclear Information System (INIS)

Sweet, Colin.

1989-01-01

Fusion power requires an exceptionally long development time and its future depends on the changing perspectives society uses to evaluate resources in the long term. For 40 years fusion technology developed within a decision making context dominated by technical-political interests, and characterized by a bias towards overoptimism about the future. That is now changing. This article contends that we are still a long way from making rational assessments of large technological projects. However, feasibility for fusion will have to be tested by social criteria at least as important as those used for scientific feasibility. (author)

U. S. Fusion Energy Future

International Nuclear Information System (INIS)

Schmidt, John A.; Jassby, Dan; Larson, Scott; Pueyo, Maria; Rutherford, Paul H.

2000-01-01

Fusion implementation scenarios for the US have been developed. The dependence of these scenarios on both the fusion development and implementation paths has been assessed. A range of implementation paths has been studied. The deployment of CANDU fission reactors in Canada and the deployment of fission reactors in France have been assessed as possible models for US fusion deployment. The waste production and resource (including tritium) needs have been assessed. The conclusion that can be drawn from these studies is that it is challenging to make a significant impact on energy production during this century. However, the rapid deployment of fission reactors in Canada and France support fusion implementation scenarios for the US with significant power production during this century. If the country can meet the schedule requirements then the resource needs and waste production are found to be manageable problems

Future with fusion power

International Nuclear Information System (INIS)

Hirschfeld, F.

1977-01-01

This article reviews several current approaches to the development of nuclear fusion power sources by the year 2000. First mentioned is the only project to develop a nonpolluting, radiation-free source by using only natural and nonradioactive isotopes (nuclei of deuterium, helium 3 and boron) as ''advanced'' fuels. This system will also be capable of direct conversion of the released energy into electricity. Next described is the PACER concept, in which thermonuclear burning of deuterium occurs in fusion explosion taking place underground (e.g., in a salt dome). The released energy is absorbed in high-pressure steam which is then piped to a surface heat exchanger to provide steam for a turbogenerator. After filtration, the steam is returned. The PACER system also produces fissionable fuel. The balance of the article reviews three ''magnetic fusion'' approaches. Tokamak, mirror and theta pinch systems utilize magnetic fields to confine a plasma for either pulsed or steady-state operation. The tokamak and theta pinch are toroidal in shape, while the mirror can be thought of as a magnetic field configuration of roughly tubular shape that confines the plasma by means of higher fields at the ends than at its center. The tokamak approach accounts for about 65 percent of the magnetic fusion research and development, while theta pinches and mirrors represent about 15 percent each. Refs

Design of force-cooled conductors for large fusion magnets

Energy Technology Data Exchange (ETDEWEB)

Dresner, L.; Lue, J.W.

1977-01-01

Conductors cooled by supercritical helium in forced convection are under active consideration for large toroidal fusion magnets. One of the central problems in designing such force cooled conductors is to maintain an adequate stability margin while keeping the pumping power tolerably low. A method has been developed for minimizing the pumping power for fixed stability by optimally choosing the matrix-to-superconductor and the metal-to-helium ratios. Such optimized conductors reduce pumping power requirements for fusion size magnets to acceptable limits. Furthermore, the mass flow and hence pumping losses can be varied through a magnet according to the local magnetic field and magnitude of desired stability margin. Force cooled conductors give flexibility in operation, permitting, for example, higher fields to be obtained than originally intended by lowering the bath temperature or increasing the pumping power or both. This flexibility is only available if the pumping power is low to begin with. Scaling laws for the pumping requirement and stability margin as functions of operating current density, number of strands and such physical parameters as stabilizer resistivity and critical current density, have been proved. Numerical examples will be given for design of conductors intended for use in large toroidal fusion magnet systems.

Design of force-cooled conductors for large fusion magnets

International Nuclear Information System (INIS)

Dresner, L.; Lue, J.W.

1977-01-01

Conductors cooled by supercritical helium in forced convection are under active consideration for large toroidal fusion magnets. One of the central problems in designing such force cooled conductors is to maintain an adequate stability margin while keeping the pumping power tolerably low. A method has been developed for minimizing the pumping power for fixed stability by optimally choosing the matrix-to-superconductor and the metal-to-helium ratios. Such optimized conductors reduce pumping power requirements for fusion size magnets to acceptable limits. Furthermore, the mass flow and hence pumping losses can be varied through a magnet according to the local magnetic field and magnitude of desired stability margin. Force cooled conductors give flexibility in operation, permitting, for example, higher fields to be obtained than originally intended by lowering the bath temperature or increasing the pumping power or both. This flexibility is only available if the pumping power is low to begin with. Scaling laws for the pumping requirement and stability margin as functions of operating current density, number of strands and such physical parameters as stabilizer resistivity and critical current density, have been proved. Numerical examples will be given for design of conductors intended for use in large toroidal fusion magnet systems

Heavy-ion fusion: future promise and future directions

International Nuclear Information System (INIS)

Dudziak, D.J.; Saylor, W.W.; Pendergrass, J.H.

1986-01-01

The previous papers in this heavy-ion fusion special session have described work performed as part of the Heavy-Ion Fusion Systems Assessment (HIFSA) Project. Key technical issues in the design and costing of targets, induction linacs, beam transport, reactor, balance of plant, and systems integration have been identified and described. The HIFSA systems model was used to measure the relative value of improvements in physics understanding and technology developments in many different areas. Within the limits of our 1986 knowledge and imagination, this study defines the most attractive heavy-ion fusion (HIF) power plant concepts. The project has deliberately avoided narrowing the focus to a point facility design; thus, the generic systems modeling capability developed in the process allows for relative comparisons among design options. We will describe what are thought to be achievable breakthroughs and what the relative significance of the breakthroughs will be, although the specific mechanism for achieving some breakthroughs may not be clear at this point. This degree of optimism concerning such breakthroughs is probably at least as conservative as that used in other fusion assessments

Large ceramics for fusion applications

International Nuclear Information System (INIS)

Hauth, W.E.; Stoddard, S.D.

1979-01-01

Prominent ceramic raw materials and products manufacturers were surveyed to determine the state of the art for alumina ceramic fabrication. This survey emphasized current capabilities and limitations for fabrication of large, high-density, high-purity, complex shapes. Some directions are suggested for future needs and development. Ceramic-to-ceramic sealing has applications for several technologies that require large and/or complex vacuum-tight ceramic shapes. Information is provided concerning the assembly of complex monolithic ceramic shapes by bonding of subassemblies at temperatures ranging from 450 to 1500 0 C. Future applications and fabrication techniques for various materials are presented

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

Potential Fusion Market for Hydrogen Production Under Environmental Constraints

International Nuclear Information System (INIS)

Konishi, Satoshi

2005-01-01

Potential future hydrogen market and possible applications of fusion were analyzed. Hydrogen is expected as a major energy and fuel mediun for the future, and various processes for hydrogen production can be considered as candidates for the use of fusion energy. In order to significantly contribute to reduction of CO 2 emission, fusion must be deployed in developing countries, and must substitute fossil based energy with synthetic fuel such as hydrogen. Hydrogen production processes will have to evaluated and compared from the aspects of energy efficiency and CO 2 emission. Fusion can provide high temperature heat that is suitable for vapor electrolysis, thermo-chemical water decomposition and steam reforming with biomass waste. That is a possible advantage of fusion over renewables and Light water power reactor. Despite of its technical difficulty, fusion is also expected to have less limitation for siting location in the developing countries. Under environmental constraints, fusion has a chance to be a major primary energy source, and production of hydrogen enhances its contribution, while in 'business as usual', fusion will not be selected in the market. Thus if fusion is to be largely used in the future, meeting socio-economic requirements would be important

Discussion on Safety Analysis and Regulatory Framework for the Future Fusion Reactors

Energy Technology Data Exchange (ETDEWEB)

Kang, Myoung-suk; Oh, Kyemin; Heo, Gyunyoung [Kyung Hee University, Yongin (Korea, Republic of)

2015-05-15

This study aims to secure the core original technologies and expand the base of domestic specialist at a fusion area by pursuing and developing nonprocurement technologies for ITER. From this project, the latest technical data and experiences have been recorded for the development of the safety regulation and safety-related design criteria of the future fusion reactors in Korea. In this context, this paper discusses on the progress of surveying the ITER licensing process and regulatory issues revealed. The regulation and licensing process for a fusion power plant has been expected to be quite different due to unique and unforeseen properties differently from the conventional nuclear facilities. To overcome this, not only various safety issues should be analyzed, but safety objectives, regulatory requirements, and design variables should also be established in detailed design phase. We expect our survey will contribute on the discussion to establish general and technical safety principles for national fusion power plant technology plans.

Fusion technology development: role of fusion facility upgrades and fission test reactors

International Nuclear Information System (INIS)

Hsu, P.Y.; Deis, G.A.; Longhurst, G.R.; Miller, L.G.; Schmunk, R.E.

1983-01-01

The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. The authors show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

Fusion technology development: role of fusion facility upgrades and fission test reactors

International Nuclear Information System (INIS)

Hsu, P.Y.; Deis, G.A.; Miller, L.G.; Longhurst, G.R.; Schmunk, R.E.

1983-01-01

The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. We will show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

Development of large insulator rings for the TOKAMAK Fusion Test Reactor

International Nuclear Information System (INIS)

Brown, T.; Tobin, A.

1977-01-01

Research and development leading to the manufacture of large ceramic insulator rings for the TFTR (TOKAMAK Fusion Test Reactor). Material applictions, fabrication approach and testing activities are highlighted

Superconductivity Engineering and Its Application for Fusion 3.Superconducting Technology as a Gateway to Future Technology

Science.gov (United States)

Asano, Katsuhiko

Hopes for achieving a new source of energy through nuclear fusion rest on the development of superconducting technology that is needed to make future equipments more energy efficient as well as increase their performance. Superconducting technology has made progress in a wide variety of fields, such as energy, life science, electronics, industrial use and environmental improvement. It enables the actualization of equipment that was unachievable with conventional technology, and will sustain future “IT-Based Quality Life Style”, “Sustainable Environmental” and “Advanced Healthcare” society. Besides coil technology with high magnetic field performance, superconducting electoronics or device technology, such as SQUID and SFQ-circuit, high temperature superconducting material and advanced cryogenics technology might be great significance in the history of nuclear fusion which requires so many wide, high and ultra technology. Superconducting technology seems to be the catalyst for a changing future society with nuclear fusion. As society changes, so will superconducting technology.

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)

Fusion tritium program in Japan

International Nuclear Information System (INIS)

Okamoto, M.; Yoshida, H.; Naruse, Y.

1988-01-01

Nuclear Fusion Council, Atomic Energy Commission of Japan, has started to review the nuclear fusion R and D plan for the next stage, post JT-60. The council launched a subcommittee on fundamental issues in the nuclear fusion development in 1985, for review of the basic strategy of a development plan. The subcommittee presented an interim report in Feb. 1986 after 6 months discussion and the report was approved by the Nuclear Fusion Council. Two major R and D programs described in the interim report are the development of a Tokamak type large facility and the comprehensive development of the fusion reactor technology. The latter means to promote the reactor technologies which will be essential in the future to construct not only a D/T burning but also a DEMO reactor. The Nuclear Fusion Development Program in Japan is shown. The interim report recommended to organize two subcommittees to establish an integrated national R and D plan; one was for the design of the next step large facility and the other was for the R and program of the fusion technology. The subcommittee for the latter consisted of 7 working groups; one of them was organized for the tritium technology

Development of large insulator rings for the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Brown, T.; Tobin, A.

1978-01-01

This paper discusses research and development leading to the manufacture of large ceramic insulator rings for the TFTR (TOKAMAK Fusion Test Reactor). Material applications, fabrication approach and testing activities are highlighted

Implications of the second law for future directions in controlled fusion research

International Nuclear Information System (INIS)

Roth, J.R.; Miley, G.H.

1980-01-01

Many existing energy related technologies have developed under the influence of social, economic, or state of the art constraints, and they cannot be viewed as optimum systems according to the second law of thermodynamics. Controlled fusion research presents an opportunity to optimize a nascent technology with respect to second law considerations in order to develop a practical energy source. In its present state of development, fusion research offers several independent approaches that may result in a net power producing fusion reactor. This paper discusses how second law considerations might be used to narrow the range of choices that must be made among various fusion fuel cycles. From a second law point of view, the most desirable fusion reactors are those for which the energy of charged particles can be converted directly into d.c. electrical power, while still allowing the energy that could be recovered by an efficient high-temperature 'blanket' to be transported largely by radiation. Fusion research in all major industrialized countries is developing the deuterium-tritium (D-T) fuel cycle for first-generation fusion power plants. It will be shown that other fuel cycles have significant advantages over the D-T fuel cycle according to second law principles. (author)

Security on the US Fusion Grid

Energy Technology Data Exchange (ETDEWEB)

Burruss, Justin R.; Fredian, Tom W.; Thompson, Mary R.

2005-06-01

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER.

Security on the US Fusion Grid

International Nuclear Information System (INIS)

Burruss, Justin R.; Fredian, Tom W.; Thompson, Mary R.

2005-01-01

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER

Security on the US fusion grid

International Nuclear Information System (INIS)

Burruss, J.R.; Fredian, T.W.; Thompson, M.R.

2006-01-01

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This has led to the development of the U.S. fusion grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large U.S. fusion research facilities and with users both in the U.S. and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER

Inertial fusion research at Lawrence Livermore National Laboratory: program status and future applications

International Nuclear Information System (INIS)

Meier, W.R.; Hogan, W.J.

1986-01-01

The objectives of the Lawrence Livermore National Laboratory (LLNL) Laser Fusion Program are to understand and develop the science and technology required to utilize inertial confinement fusion (ICF) for both military and commercial applications. The results of recent experiments are described. We point out the progress in our laser studies, where we continue to develop and test the concepts, components, and materials for present and future laser systems. While there are many potential commercial applications of ICF, we limit our discussions to electric power production

Fusion power economy of scale

International Nuclear Information System (INIS)

Dolan, T.J.

1993-01-01

In the next 50 yr, the world will need to develop hundreds of gigawatts of non-fossil-fuel energy sources for production of electricity and fuels. Nuclear fusion can probably provide much of the required energy economically, if large single-unit power plants are acceptable. Large power plants are more common than most people realize: There are already many multiple-unit power plants producing 2 to 5 GW(electric) at a single site. The cost of electricity (COE) from fusion energy is predicted to scale as COE ∼ COE 0 (P/P 0 ) -n , where P is the electrical power, the subscript zero denotes reference values, and the exponent n ∼ 0.36 to 0.7 in various designs. The validity ranges of these scalings are limited and need to be extended by future work. The fusion power economy of scale derives from four interrelated effects: improved operations and maintenance costs; scaling of equipment unit costs; a geometric effect that increases the mass power density; and reduction of the recirculating power fraction. Increased plasma size also relaxes the required confinement parameters: For the same neutron wall loading, larger tokamaks can use lower magnetic fields. Fossil-fuel power plants have a weaker economy of scale than fusion because the fuel costs constitute much of their COE. Solar and wind power plants consist of many small units, so they have little economy of scale. Fission power plants have a strong economy of scale but are unable to exploit it because the maximum unit size is limited by safety concerns. Large, steady-state fusion reactors generating 3 to 6 GW(electric) may be able to produce electricity for 4 to 5 cents/kW·h, which would be competitive with other future energy sources. 38 refs., 6 figs., 6 tabs

Need for research and development in fusion: Economical energy for a sustainable future with low environmental impact

International Nuclear Information System (INIS)

Logan, B.G.; Perkins, L.J.; Moir, R.W.; Ryutov, D.D.

1995-01-01

Fusion, advanced fission, and solar-electric plants are the only unlimited nonfossil options for a sustainable energy future for the world. Fusion poses the only indigenous fuel reserve that will last as long as the earth itself lasts. However, continued innovation and diversity in fusion R ampersand D will be required to meet its economic goal. The long-term nature of fusion research means that the required R ampersand D investment will not come from the private sector. However, once fusion is realized commercially, the dividend for humanity will be profound in terms of the welfare of the global community. We should also not underestimate the huge potential export opportunities that would then open up for industry. Federal energy R ampersand D at nearly 1% of U.S. energy costs is prudent and justified to allow pursuit of all three primary energy options for a sustainable energy future. Multiple parallel paths are essential to ensure success. The projected timescale for significant shortfalls in world energy supply to become apparent is nearly 30 to 40 yr depending on assumptions. The time to develop fusion from near-term R ampersand D through significant commercial market penetration is at least of the same order, so its development must not be delayed. 6 refs., 2 figs

Nuclear fusion, an energy source of the future

International Nuclear Information System (INIS)

Koeppendoerfer, W.

1994-01-01

The paper discusses the possibility to obtain energy by nuclear fusion. It deals successively with: The physical bases of nuclear fusion, research and development with a view to harnessing nuclear fusion, properties of a fusion reactor, and programme and timetable to economic exploitation. (orig./UA) [de

Physics, systems analysis and economics of fusion power plants

International Nuclear Information System (INIS)

Ward, D.J.

2006-01-01

Fusion power is being developed because of its large resource base, low environmental impact and high levels of intrinsic safety. It is important, however, to investigate the economics of a future fusion power plant to check that the electricity produced can, in fact, have a market. Using systems code analysis, including costing algorithms, this paper gives the cost of electricity expected from a range of fusion power plants, assuming that they are brought into successful operation. Although this paper does not purport to show that a first generation of fusion plants is likely to be the cheapest option for a future energy source, such plants look likely to have a market in some countries even without taking account of fusion's environmental advantages. With improved technological maturity fusion looks likely to have a widespread potential market particularly if the value of its environmental advantages are captured, for instance through avoiding a carbon tax. (author)

Monitoring and Information Fusion for Search and Rescue Operations in Large-Scale Disasters

National Research Council Canada - National Science Library

Nardi, Daniele

2002-01-01

... for information fusion with application to search-and-rescue and large scale disaster relief. The objective is to develop and to deploy tools to support the monitoring activities in an intervention caused by a large-scale disaster...

Data security on the national fusion grid

Energy Technology Data Exchange (ETDEWEB)

Burruss, Justine R.; Fredian, Tom W.; Thompson, Mary R.

2005-06-01

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER.

Data security on the national fusion grid

International Nuclear Information System (INIS)

Burruss, Justine R.; Fredian, Tom W.; Thompson, Mary R.

2005-01-01

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER

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

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

Development of large components for the fusion reactor vacuum circuits

International Nuclear Information System (INIS)

Perinic, D.; Lorrain, C.

1986-06-01

The Commission of the European Communities appointed in mid-1983 the Centre d'Etudes Nucleaires de Saclay and the Kernforschungszentrum Karlsruhe GmbH to investigate whether large vacuum components for use in the fusion machine can be built. The following individual targets have been defined for studies under this project: - Elaboration of technical specifications for large components. - Investigation of the feasibility. - Specification of the tests required and planning of a testing facility. The plasma chamber pumping system is essentially concerned

IEC fusion: The future power and propulsion system for space

International Nuclear Information System (INIS)

Hammond, Walter E.; Coventry, Matt; Miley, George H.; Nadler, Jon; Hanson, John; Hrbud, Ivana

2000-01-01

Rapid access to any point in the solar system requires advanced propulsion concepts that will provide extremely high specific impulse, low specific power, and a high thrust-to-power ratio. Inertial Electrostatic Confinement (IEC) fusion is one of many exciting concepts emerging through propulsion and power research in laboratories across the nation which will determine the future direction of space exploration. This is part of a series of papers that discuss different applications of the Inertial Electrostatic Confinement (IEC) fusion concept for both in-space and terrestrial use. IEC will enable tremendous advances in faster travel times within the solar system. The technology is currently under investigation for proof of concept and transitioning into the first prototype units for commercial applications. In addition to use in propulsion for space applications, terrestrial applications include desalinization plants, high energy neutron sources for radioisotope generation, high flux sources for medical applications, proton sources for specialized medical applications, and tritium production

Fusion Power measurement at ITER

Energy Technology Data Exchange (ETDEWEB)

Bertalot, L.; Barnsley, R.; Krasilnikov, V.; Stott, P.; Suarez, A.; Vayakis, G.; Walsh, M. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

2015-07-01

Nuclear fusion research aims to provide energy for the future in a sustainable way and the ITER project scope is to demonstrate the feasibility of nuclear fusion energy. ITER is a nuclear experimental reactor based on a large scale fusion plasma (tokamak type) device generating Deuterium - Tritium (DT) fusion reactions with emission of 14 MeV neutrons producing up to 700 MW fusion power. The measurement of fusion power, i.e. total neutron emissivity, will play an important role for achieving ITER goals, in particular the fusion gain factor Q related to the reactor performance. Particular attention is given also to the development of the neutron calibration strategy whose main scope is to achieve the required accuracy of 10% for the measurement of fusion power. Neutron Flux Monitors located in diagnostic ports and inside the vacuum vessel will measure ITER total neutron emissivity, expected to range from 1014 n/s in Deuterium - Deuterium (DD) plasmas up to almost 10{sup 21} n/s in DT plasmas. The neutron detection systems as well all other ITER diagnostics have to withstand high nuclear radiation and electromagnetic fields as well ultrahigh vacuum and thermal loads. (authors)

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.)

Plasma facing materials and components for future fusion devices - development, characterization and performance under fusion specific loading conditions

Energy Technology Data Exchange (ETDEWEB)

Linke, J. [Forschungszentrum Juelich (Germany). Inst. fuer Plasmaphysik

2006-04-15

The plasma exposed components in existing and future fusion devices are strongly affected by the plasma material interaction processes. These mechanisms have a strong influence on the plasma performance; in addition they have major impact on the lifetime of the plasma facing armour and the joining interface between the plasma facing material (PFM) and the heat sink. Besides physical and chemical sputtering processes, high heat quasi-stationary fluxes during normal and intense thermal transients are of serious concern for the engineers who develop reliable wall components. In addition, the material and component degradation due to intense fluxes of energetic neutrons is another critical issue in D-T-burning fusion devices which requires extensive RandD. This paper presents an overview on the materials development and joining, the testing of PFMs and components, and the analysis of the neutron irradiation induced degradation.

Plasma facing materials and components for future fusion devices - development, characterization and performance under fusion specific loading conditions

International Nuclear Information System (INIS)

Linke, J.

2006-01-01

The plasma exposed components in existing and future fusion devices are strongly affected by the plasma material interaction processes. These mechanisms have a strong influence on the plasma performance; in addition they have major impact on the lifetime of the plasma facing armour and the joining interface between the plasma facing material (PFM) and the heat sink. Besides physical and chemical sputtering processes, high heat quasi-stationary fluxes during normal and intense thermal transients are of serious concern for the engineers who develop reliable wall components. In addition, the material and component degradation due to intense fluxes of energetic neutrons is another critical issue in D-T-burning fusion devices which requires extensive RandD. This paper presents an overview on the materials development and joining, the testing of PFMs and components, and the analysis of the neutron irradiation induced degradation

Plasma facing materials and components for future fusion devices—development, characterization and performance under fusion specific loading conditions

Science.gov (United States)

Linke, J.

2006-04-01

The plasma exposed components in existing and future fusion devices are strongly affected by the plasma material interaction processes. These mechanisms have a strong influence on the plasma performance; in addition they have major impact on the lifetime of the plasma facing armour and the joining interface between the plasma facing material (PFM) and the heat sink. Besides physical and chemical sputtering processes, high heat quasi-stationary fluxes during normal and intense thermal transients are of serious concern for the engineers who develop reliable wall components. In addition, the material and component degradation due to intense fluxes of energetic neutrons is another critical issue in D-T-burning fusion devices which requires extensive R&D. This paper presents an overview on the materials development and joining, the testing of PFMs and components, and the analysis of the neutron irradiation induced degradation.

Modelling irradiation effects in fusion materials

DEFF Research Database (Denmark)

Victoria, M.; Dudarev, S.; Boutard, J.L.

2007-01-01

We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future development. Large-scale density functional theory (DFT) calculations reveal the structure of the point defects in α-Fe, and highlight the crucial...

An investigation on detection and measurement of fusion neutron spectrum and radiation flux in large tokamak

International Nuclear Information System (INIS)

Yang Jinwei; Li Wenzhong; Zhang Wei

2003-01-01

The detection methods, detectors and spectrometers of D-D and D-T fusion neutron have been overviewed in large tokamaks. Some options are proposed for developing new detection systems of fusion neutrons suitable to the HL-2A tokamak. (authors)

Fusion technology 1992

International Nuclear Information System (INIS)

Ferro, C.; Gasparatto, M.; Knoepfel, H.

1993-01-01

The aim of the biennial series of symposia on the title subject, organized by the European Fusion Laboratories, is the exchange of information on the design, construction and operation of fusion experiments and on the technology being developed for the next step devices and fusion reactors. The coverage of the volume includes the technological aspects of fusion reactors in relation to new developments, this forming a guideline for the definition of future work. These proceedings comprise three volumes and contain both the invited lectures and contributed papers presented at the symposium which was attended by 569 participants from around the globe. The 343 papers, including 12 invited papers, characterize the increasing interest of industry in the fusion programme, giving a broad and current overview on the progress and trends fusion technology is experiencing now, as well as indicating the future for fusion devices

Future directions in inertial confinement fusion

International Nuclear Information System (INIS)

Bodner, S.E.

1992-01-01

The author discusses future directions for the ICF program. At this time there is still uncertainty on a number of key issues necessary to decide on what type of a National Ignition Facility should be constructed. Mechanisms are in place to answer these questions. The author offers his opinions of where the program is likely to proceed. Technology wise indications are that direct drive heating has the best chance of reaching ignition and high gain. This has the advantage of making all three major user programs happy, namely weapons physics, weapons effects, and electrical energy. The demand for and price of energy in the country will have a major impact on the way the program is developed. From the laser fusion side the most promising drivers at present seem to be KrF lasers, and a major concern for these systems is whether the peak to valley nonuniformities can be reduced to the 1 to 2% level when delivered to the target in order to avoid driving instabilities

An Assessment of the Economics of Future Electric Power Generation Options and the Implications for Fusion

International Nuclear Information System (INIS)

Delene, J.G.; Hadley, S.; Reid, R.L.; Sheffield, J.; Williams, K.A.

1999-01-01

This study examines the potential range of electric power costs for some major alternatives to fusion electric power generation when it is ultimately deployed in the middle of the 21st century and, thus, offers a perspective on the cost levels that fusion must achieve to be competitive. The alternative technologies include coal burning, coal gasification, natural gas, nuclear fission, and renewable energy. The cost of electricity (COE) from the alternatives to fusion should remain in the 30-50 mils/kWh (1999 dollars) range of today in carbon sequestration is not needed, 30-60 mils/kWh if sequestration is required, or as high as 75 mils/kWh for the worst-case scenario for cost uncertainty. The reference COE range for fusion was estimated at 70-100 nmils/kWh for 1- to 1.3-GW(e) scale power plants. Fusion costs will have to be reduced and/or alternative concepts derived before fusion will be competitive with the alternatives for the future production of electricity. Fortunately, there are routes to achieve this goal

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.

Energy Logic (EL): a novel fusion engine of multi-modality multi-agent data/information fusion for intelligent surveillance systems

Science.gov (United States)

Rababaah, Haroun; Shirkhodaie, Amir

2009-04-01

The rapidly advancing hardware technology, smart sensors and sensor networks are advancing environment sensing. One major potential of this technology is Large-Scale Surveillance Systems (LS3) especially for, homeland security, battlefield intelligence, facility guarding and other civilian applications. The efficient and effective deployment of LS3 requires addressing number of aspects impacting the scalability of such systems. The scalability factors are related to: computation and memory utilization efficiency, communication bandwidth utilization, network topology (e.g., centralized, ad-hoc, hierarchical or hybrid), network communication protocol and data routing schemes; and local and global data/information fusion scheme for situational awareness. Although, many models have been proposed to address one aspect or another of these issues but, few have addressed the need for a multi-modality multi-agent data/information fusion that has characteristics satisfying the requirements of current and future intelligent sensors and sensor networks. In this paper, we have presented a novel scalable fusion engine for multi-modality multi-agent information fusion for LS3. The new fusion engine is based on a concept we call: Energy Logic. Experimental results of this work as compared to a Fuzzy logic model strongly supported the validity of the new model and inspired future directions for different levels of fusion and different applications.

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

Telescope-based cavity for negative ion beam neutralization in future fusion reactors.

Science.gov (United States)

Fiorucci, Donatella; Hreibi, Ali; Chaibi, Walid

2018-03-01

In future fusion reactors, heating system efficiency is of the utmost importance. Photo-neutralization substantially increases the neutral beam injector (NBI) efficiency with respect to the foreseen system in the International Thermonuclear Experimental Reactor (ITER) based on a gaseous target. In this paper, we propose a telescope-based configuration to be used in the NBI photo-neutralizer cavity of the demonstration power plant (DEMO) project. This configuration greatly reduces the total length of the cavity, which likely solves overcrowding issues in a fusion reactor environment. Brought to a tabletop experiment, this cavity configuration is tested: a 4 mm beam width is obtained within a ≃1.5  m length cavity. The equivalent cavity g factor is measured to be 0.038(3), thus confirming the cavity stability.

Vacuum engineering for fusion research and fusion reactors

International Nuclear Information System (INIS)

Pittenger, L.C.

1976-01-01

The following topics are described: (1) surface pumping by cryogenic condensation, (2) operation of large condensing cryopumps, (3) pumping for large fusion experiments, and (4) vacuum technology for fusion reactors

Laser Fusion: status, future, and tritium control

International Nuclear Information System (INIS)

Coyle, P.E.

1978-11-01

At Livermore the 10 kJ, 20 to 30 TW Shiva facility is now operational and producing regular new fusion results. Design work has begun on a 200 to 300 TW laser designed to carry the program through the first breakeven demonstration experiments in the mid-1980's. Confidence in reaching this goal is based on the significant progress we have made in state-of-the-art, high-power Nd:glass laser technology, in experimental laser fusion and laser plasma interaction physics, and in theoretical and analytical computer codes which reliably model and predict experimental results. For all of these experiments, a variety of fusion targets are being fabricated in the laboratory, and the control and handling of tritium is now a regular and routine part of ongoing inertial fusion experiments. Target design with gains of about 1000 have been studied and the means to mass produce such pellets at low cost are also being developed

Fusion power

International Nuclear Information System (INIS)

Hancox, R.

1981-01-01

The principles of fusion power, and its advantages and disadvantages, are outlined. Present research programmes and future plans directed towards the development of a fusion power reactor, are summarized. (U.K.)

Costs of magnets for large fusion power reactors: Phase I, cost of superconductors for dc magnets

International Nuclear Information System (INIS)

Powell, J.R.

1972-01-01

Projections are made for dc magnet conductor costs for large fusion power reactors. A mature fusion economy is assumed sometime after 2000 A. D. in which approximately 90,000 MW(e) of fusion reactors are constructed/year. State of the art critical current vs. field characteristics for superconductors are used in these projections. Present processing techniques are used as a basis for the design of large plants sized to produce approximately one-half of the conductor needed for the fusion magnets. Multifilamentary Nb-Ti, Pb-Bi in glass fiber, GE Nb 3 Sn tape, Linde plasma sprayed Nb 3 Sn tape, and V 3 Ga tape superconductors are investigated, together with high purity aluminum cryoconductor. Conductor costs include processing costs [capital (equipment plus buildings), labor, and operating] and materials costs. Conductor costs are compared for two sets of material costs: current (1971 A. D.) costs, and projected (after 2000 A. D.) costs. (U.S.)

Long-term modelling of Carbon Capture and Storage, Nuclear Fusion, and large-scale District Heating

DEFF Research Database (Denmark)

Grohnheit, Poul Erik; Korsholm, Søren Bang; Lüthje, Mikael

2011-01-01

before 2050. The modelling tools developed by the International Energy Agency (IEA) Implementing Agreement ETSAP include both multi-regional global and long-term energy models till 2100, as well as national or regional models with shorter time horizons. Examples are the EFDA-TIMES model, focusing...... on nuclear fusion and the Pan European TIMES model, respectively. In the next decades CCS can be a driver for the development and expansion of large-scale district heating systems, which are currently widespread in Europe, Korea and China, and with large potentials in North America. If fusion will replace...... fossil fuel power plants with CCS in the second half of the century, the same infrastructure for heat distribution can be used which will support the penetration of both technologies. This paper will address the issue of infrastructure development and the use of CCS and fusion technologies using...

Welding for fusion grade neutral beam components - requirements, challenges, experiences and learnings

International Nuclear Information System (INIS)

Joshi, Jaydeep; Patel, Hitesh; Yadav, Ashish; Rotti, Chandramouli; Bandyopadhyay, Mainak; Chakraborty, Arun

2016-01-01

Negative ion based Neutral Beam Injectors (NBI) are the integral part of large size fusion devices where Neutral Beams of Hydrogen/Deuterium atoms are injected into the fusion reactor to heat the plasma, drive a plasma current, provide fuel to the plasma and also help to diagnose the plasma through spectroscopic measurements. The presentation shares the experiences of handling, some of special welding activities applicable for fusion prototypes developments, experiments, methodology developed for the inspection/tests, criteria considered with the appropriate justifications. This also shares the view point of authors code should further be supplement and incorporate the fusion specific applications considering future needs. In addition, explorations to meet our future needs of welding with specific attention to indigenous developments have been described

The future of nuclear engineering

International Nuclear Information System (INIS)

Beeden, Jeffrey

2003-01-01

Today, nuclear power refers to the splitting of large uranium atoms into smaller atoms with a net release of energy. Tomorrow, nuclear power will refer to the combining of hydrogen into larger atoms with a net release of energy. Nuclear power's future is fusion. The Mechanical Engineers of tomorrow will need to be familiar with the process of creating and harnessing the energy from a fusion reaction. During the oil shortage in the 1970's, America scrambled to initiate alternative methods of producing power. Nuclear fusion was one of them. As time passes, the solution to the world's energy crisis presses the countries of the world to find alternative forms of energy; nuclear fusion may contain the answer. In the near future, the field of fusion will open up and a new wave of engineers will flood into this field. Mechanical engineers will lead the way with advances in materials, computational fluid dynamics, finite element analysis for thermal and structural systems, and heat transfer designs to optimize nuclear fusion reactors and power plants. All this effort is in anticipation of creating a sustained fusion reaction that can generate enough heat to transfer to steam in order to generate electric power to sustain the fusion reaction and introduce power to the grid. (author)

Superconducting magnets for fusion applications

International Nuclear Information System (INIS)

Henning, C.D.

1987-01-01

Fusion magnet technology has made spectacular advances in the past decade; to wit, the Mirror Fusion Test Facility and the Large Coil Project. However, further advances are still required for advanced economical fusion reactors. Higher fields to 14 T and radiation-hardened superconductors and insulators will be necessary. Coupled with high rates of nuclear heating and pulsed losses, the next-generation magnets will need still higher current density, better stability and quench protection. Cable-in-conduit conductors coupled with polyimide insulations and better steels seem to be the appropriate path. Neutron fluences up to 10 19 neutrons/cm 2 in niobium tin are achievable. In the future, other amorphous superconductors could raise these limits further to extend reactor life or decrease the neutron shielding and corresponding reactor size

The fusion of large scale classified side-scan sonar image mosaics.

Science.gov (United States)

Reed, Scott; Tena, Ruiz Ioseba; Capus, Chris; Petillot, Yvan

2006-07-01

This paper presents a unified framework for the creation of classified maps of the seafloor from sonar imagery. Significant challenges in photometric correction, classification, navigation and registration, and image fusion are addressed. The techniques described are directly applicable to a range of remote sensing problems. Recent advances in side-scan data correction are incorporated to compensate for the sonar beam pattern and motion of the acquisition platform. The corrected images are segmented using pixel-based textural features and standard classifiers. In parallel, the navigation of the sonar device is processed using Kalman filtering techniques. A simultaneous localization and mapping framework is adopted to improve the navigation accuracy and produce georeferenced mosaics of the segmented side-scan data. These are fused within a Markovian framework and two fusion models are presented. The first uses a voting scheme regularized by an isotropic Markov random field and is applicable when the reliability of each information source is unknown. The Markov model is also used to inpaint regions where no final classification decision can be reached using pixel level fusion. The second model formally introduces the reliability of each information source into a probabilistic model. Evaluation of the two models using both synthetic images and real data from a large scale survey shows significant quantitative and qualitative improvement using the fusion approach.

Effects of large-angle Coulomb collisions on inertial confinement fusion plasmas.

Science.gov (United States)

Turrell, A E; Sherlock, M; Rose, S J

2014-06-20

Large-angle Coulomb collisions affect the rates of energy and momentum exchange in a plasma, and it is expected that their effects will be important in many plasmas of current research interest, including in inertial confinement fusion. Their inclusion is a long-standing problem, and the first fully self-consistent method for calculating their effects is presented. This method is applied to "burn" in the hot fuel in inertial confinement fusion capsules and finds that the yield increases due to an increase in the rate of temperature equilibration between electrons and ions which is not predicted by small-angle collision theories. The equilibration rate increases are 50%-100% for number densities of 10(30)  m(-3) and temperatures around 1 keV.

Mars manned fusion spaceship

International Nuclear Information System (INIS)

Hedrick, J.; Buchholtz, B.; Ward, P.; Freuh, J.; Jensen, E.

1991-01-01

Fusion Propulsion has an enormous potential for space exploration in the near future. In the twenty-first century, a usable and efficient fusion rocket will be developed and in use. Because of the great distance between other planets and Earth, efficient use of time, fuel, and payload is essential. A nuclear spaceship would provide greater fuel efficiency, less travel time, and a larger payload. Extended missions would give more time for research, experiments, and data acquisition. With the extended mission time, a need for an artificial environment exists. The topics of magnetic fusion propulsion, living modules, artificial gravity, mass distribution, space connection, and orbital transfer to Mars are discussed. The propulsion system is a magnetic fusion reactor based on a tandem mirror design. This allows a faster, shorter trip time and a large thrust to weight ratio. The fuel proposed is a mixture of deuterium and helium. Helium can be obtained from lunar mining. There will be minimal external radiation from the reactor resulting in a safe, efficient propulsion system

Safety analysis and evaluation methodology for fusion systems

International Nuclear Information System (INIS)

Fujii-e, Y.; Kozawa, Y.; Namba, C.

1987-03-01

Fusion systems which are under development as future energy systems have reached a stage that the break even is expected to be realized in the near future. It is desirable to demonstrate that fusion systems are well acceptable to the societal environment. There are three crucial viewpoints to measure the acceptability, that is, technological feasibility, economy and safety. These three points have close interrelation. The safety problem is more important since three large scale tokamaks, JET, TFTR and JT-60, start experiment, and tritium will be introduced into some of them as the fusion fuel. It is desirable to establish a methodology to resolve the safety-related issues in harmony with the technological evolution. The promising fusion system toward reactors is not yet settled. This study has the objective to develop and adequate methodology which promotes the safety design of general fusion systems and to present a basis for proposing the R and D themes and establishing the data base. A framework of the methodology, the understanding and modeling of fusion systems, the principle of ensuring safety, the safety analysis based on the function and the application of the methodology are discussed. As the result of this study, the methodology for the safety analysis and evaluation of fusion systems was developed. New idea and approach were presented in the course of the methodology development. (Kako, I.)

Surface effects in controlled thermonuclear fusion

International Nuclear Information System (INIS)

Kaminsky, M.

1975-08-01

During the operation of large size plasma facilities and future controlled thermonuclear fusion reactors the surfaces of such major components as container walls, beam limiters, diverter walls and beam-dump walls of the injector region will be exposed to particle and photon bombardment from primary plasma radiations and from secondary radiations. Such radiations can cause, for example, physical and chemical sputtering, blistering, particle- and photon-impact induced desorption, secondary electron and x-ray emission, backscattering, nuclear reactions, photo-decomposition of surface compounds, photocatalysis, and vaporization. Such effects in turn can (a) seriously damage and erode the bombarded surface and (b) release major quantities of impurities which will contaminate the plasma. The effects of some of the major surface phenomena on the operation of plasma facilities and future fusion reactors are discussed

The Contribution of Fusion to Sustainable Development

International Nuclear Information System (INIS)

Ward, D.

2006-01-01

The world demand for energy is projected to more than double over the next 50 years, indeed this will be essential to bring much of the world out of poverty. At the same time there is increasing pressure to substantially reduce atmospheric pollution, most notably of carbon dioxide. Together, these conflicting goals drive a need to produce enormous amounts of non-carbon energy supply, much greater than our total present energy supply. This presents an enormous challenge. As one of very few options for large-scale, non-carbon future supply of energy, fusion has the potential to make an important contribution to sustained energy supplies. Fusion's advantages of large fuel reserves, low atmospheric emissions and high levels of safety make it an important consideration in future energy strategies. - Fuel supplies are sufficient for at least thousands of years, and probably up to millions of years, of energy use. - Atmospheric emissions of CO 2 are very low and minor emissions of other pollutants are less harmful than those from most existing energy sources. - Hazards to the public will be very low because of the high levels of passive safety. - Waste materials will require little, or no, use of repository storage. Conceptual designs of fusion power plants have been optimised against safety and environmental criteria. The optimum designs vary both with the assessed progress in the development programme and according to the weight given to different criteria. The impact of this weighting on design, and the comparison of the outcomes with other energy sources, is described. To make a contribution to sustainable development, fusion must also be economically viable to enter the energy market. The calculated cost of electricity from fusion and other technologies, both new and existing, show that, particularly in an energy market where environmental constraints are playing an increasing role, fusion can make an important contribution. (author)

Future on the ITER program. On a branch of research on nuclear fusion

International Nuclear Information System (INIS)

Masaike, Akira

2000-01-01

As a huge cost for research and development of nuclear fusion is required, some international cooperative research such as ITER program have been intended to promote, to which Japanese response is required. As the program can be understood on its meaning at a viewpoint of promotion of basic science, concept on a key of energy problem is not insufficient yet And, its effect on technical problems and environment cannot be neglected Here was shown some proposals necessity for discussion on how the program had to be promoted under consideration of these problems. When a large scale program consuming national budget will be carried out, it is natural that agreement of national peoples must be obtained. Regretfully, in Japan discussion on science program above all nuclear policy has scarcely been experienced at citizens' levels, and some bitter experiences, where the concerned have promoted it in one side under a concept without any change once decided, have been pressured without any response to scientific advancements and social changes. Therefore, future plan on the nuclear fusion must be carried out a number of thorough discussion at a wide range from various viewpoints such as its realizing feasibility, safety, economics, and so forth, to promote careful adaptabilities. And, the concerned under promotion of the program and the relatives in the academic community seem to have a responsibility to easily explain present condition and scope of the plan to not only scientists but also citizens to awake them to promote its discussion with them. (G.K.)

Characterization of a novel caudal vertebral interbody fusion in a rat tail model: An implication for future material and mechanical testing

Directory of Open Access Journals (Sweden)

Yu-Cheng Yeh

2017-02-01

Conclusion: The rat caudal disc interbody fusion model proved to be an efficient, repeatable and easily accessible model. Future research into adjuvant treatments like growth factor injection and alternative fusion materials under conditions of osteoporosis using this model would be worthwhile.

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

Non-superconducting magnet structures for near-term, large fusion experimental devices

International Nuclear Information System (INIS)

File, J.; Knutson, D.S.; Marino, R.E.; Rappe, G.H.

1980-10-01

This paper describes the magnet and structural design in the following American tokamak devices: the Princeton Large Torus (PLT), the Princeton Divertor Experiment (PDX), and the Tokamak Fusion Test Reactor (TFTR). The Joint European Torus (JET), also presented herein, has a magnet structure evolved from several European programs and, like TFTR, represents state of the art magnet and structure design

Generic structural mechanics aspects of fusion magnet systems

International Nuclear Information System (INIS)

Reich, M.; Powell, J.R.

1980-01-01

Structural mechanic requirements for future large superconducting fusion magnets are assessed. Current structural analysis methods and standards do not yet appear sufficient for a complete evaluation of such systems, under all potential operating and accident conditions. Recommendations are made for development of needed structural methods and specialized standards for fusion magnets. These include, among others, better composite structural methods with various failure criteria for metallic, as well as non-metallic materials, coupled thermal-electrical-structural codes, incorporating winding and fabrication effects, and use of probabilistic methods for life prediction. In order to help meet program goals for fusion commericialization, it is recommended that such work be initiated relatively soon. (orig.)

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.)

Review of particle-in-cell modeling for the extraction region of large negative hydrogen ion sources for fusion

Science.gov (United States)

Wünderlich, D.; Mochalskyy, S.; Montellano, I. M.; Revel, A.

2018-05-01

Particle-in-cell (PIC) codes are used since the early 1960s for calculating self-consistently the motion of charged particles in plasmas, taking into account external electric and magnetic fields as well as the fields created by the particles itself. Due to the used very small time steps (in the order of the inverse plasma frequency) and mesh size, the computational requirements can be very high and they drastically increase with increasing plasma density and size of the calculation domain. Thus, usually small computational domains and/or reduced dimensionality are used. In the last years, the available central processing unit (CPU) power strongly increased. Together with a massive parallelization of the codes, it is now possible to describe in 3D the extraction of charged particles from a plasma, using calculation domains with an edge length of several centimeters, consisting of one extraction aperture, the plasma in direct vicinity of the aperture, and a part of the extraction system. Large negative hydrogen or deuterium ion sources are essential parts of the neutral beam injection (NBI) system in future fusion devices like the international fusion experiment ITER and the demonstration reactor (DEMO). For ITER NBI RF driven sources with a source area of 0.9 × 1.9 m2 and 1280 extraction apertures will be used. The extraction of negative ions is accompanied by the co-extraction of electrons which are deflected onto an electron dump. Typically, the maximum negative extracted ion current is limited by the amount and the temporal instability of the co-extracted electrons, especially for operation in deuterium. Different PIC codes are available for the extraction region of large driven negative ion sources for fusion. Additionally, some effort is ongoing in developing codes that describe in a simplified manner (coarser mesh or reduced dimensionality) the plasma of the whole ion source. The presentation first gives a brief overview of the current status of the ion

Peaceful Uses of Fusion

Science.gov (United States)

Teller, E.

1958-07-03

Applications of thermonuclear energy for peaceful and constructive purposes are surveyed. Developments and problems in the release and control of fusion energy are reviewed. It is pointed out that the future of thermonuclear power reactors will depend upon the construction of a machine that produces more electric energy than it consumes. The fuel for thermonuclear reactors is cheap and practically inexhaustible. Thermonuclear reactors produce less dangerous radioactive materials than fission reactors and, when once brought under control, are not as likely to be subject to dangerous excursions. The interaction of the hot plasma with magnetic fields opens the way for the direct production of electricity. It is possible that explosive fusion energy released underground may be harnessed for the production of electricity before the same feat is accomplished in controlled fusion processes. Applications of underground detonations of fission devices in mining and for the enhancement of oil flow in large low-specific-yield formations are also suggested.

Laser fusion

International Nuclear Information System (INIS)

Key, M.H.; Oxford Univ.

1990-04-01

The use of lasers to drive implosions for the purpose of inertially confined fusion is an area of intense activity where progress compares favourably with that made in magnetic fusion and there are significant prospects for future development. In this brief review the basic concept is summarised and the current status is outlined both in the area of laser technology and in the most recent results from implosion experiments. Prospects for the future are also considered. (author)

Construction of a large laser fusion system

International Nuclear Information System (INIS)

Hurley, C.A.

1977-01-01

Construction of a large laser fusion machine is nearing completion at the Lawrence Livermore Laboratory (LLL). Shiva, a 20-terawatt neodymium doped glass system, will be complete in early 1978. This system will have the high power needed to demonstrate significant thermonuclear burn. Shiva will irradiate a microscopic D-T pellet with 20 separate laser beams arriving simultaneously at the target. This requires precise alignment, and stability to maintain alignment. Hardware for the 20 laser chains is composed of 140 amplifiers, 100 spatial filters, 80 isolation stages, 40 large turning mirrors, and a front-end splitter system of over 100 parts. These are mounted on a high stability, three dimensional spaceframe which serves as an optical bench. The mechanical design effort, spanning approximately 3 years, followed a classic engineering evolution. The conceptual design phase led directly to system optimization through cost and technical tradeoffs. Additional manpower was then required for detailed design and specification of hardware and fabrication. Design of long-lead items was started early in order to initiate fabrication and assembly while the rest of the design was completed. All components were ready for assembly and construction as fiscal priorities and schedules permitted

Developing the Physics Basis of Fast Ignition Experiments at Future Large Fusion-class lasers

International Nuclear Information System (INIS)

Mackinnon, A J; Key, M H; Hatchett, S; MacPhee, A G; Foord, M; Tabak, M; Town, R J; Patel, P K

2008-01-01

The Fast Ignition (FI) concept for Inertial Confinement Fusion (ICF) has the potential to provide a significant advance in the technical attractiveness of Inertial Fusion Energy (IFE) reactors. FI differs from conventional 'central hot spot' (CHS) target ignition by using one driver (laser, heavy ion beam or Z-pinch) to create a dense fuel and a separate ultra-short, ultra-intense laser beam to ignite the dense core. FI targets can burn with ∼ 3X lower density fuel than CHS targets, resulting in (all other things being equal) lower required compression energy, relaxed drive symmetry, relaxed target smoothness tolerances, and, importantly, higher gain. The short, intense ignition pulse that drives this process interacts with extremely high energy density plasmas; the physics that controls this interaction is only now becoming accessible in the lab, and is still not well understood. The attraction of obtaining higher gains in smaller facilities has led to a worldwide explosion of effort in the studies of FI. In particular, two new US facilities to be completed in 2009/2010, OMEGA/OMEGA EP and NIF-ARC (as well as others overseas) will include FI investigations as part of their program. These new facilities will be able to approach FI conditions much more closely than heretofore using direct drive (dd) for OMEGA/OMEGA EP and indirect drive (id) for NIF-ARC. This LDRD has provided the physics basis for the development of the detailed design for integrated Fast ignition experiments on these facilities on the 2010/2011 timescale. A strategic initiative LDRD has now been formed to carry out integrated experiments using NIF ARC beams to heat a full scale FI assembled core by the end of 2010

Overview of the US Magnetic Fusion Energy Program

International Nuclear Information System (INIS)

Wiffen, F.W.; Dowling, R.J.; Marton, W.A.; Eckstrand, S.A.

1990-01-01

Since the 1988 Symposium on Fusion Technology, steady progress has been made in the US Magnetic Fusion Energy Program. The large US tokamaks have reached new levels of plasma performance with associated improvements in the understanding of transport. The technology support for ongoing and future devices is similarly advancing with notable advances in magnetic, rf heating tubes, pellet injector, plasma interactive materials, tritium handling, structural materials, and system studies. Currently, a high level DOE review of the program is underway to provide recommendations for a strategic plan

Maintenance and waste treatment of tritium existing in and out of the fusion reactor systems. 6. Study of tritium confinement in the facility of a fusion reactor

International Nuclear Information System (INIS)

Kobayashi, Kazuhiro

2000-01-01

In a future fusion reactor, tritium confinement is one of the key issues for safety. Large amount of tritium (a few grams to a hundred grams level) has been handled safely at the several facilities in the world for fusion research under the multiple confinement concept. In this chapter, the study of tritium behavior in large space such as the building is described using the Caisson Assembly for Tritium Safety (CATS) study such as the final confinement and the present R and D status concerning the tritium confinement is reviewed. (author)

Confinement inertial fusion. Power reactors of nuclear fusion by lasers

International Nuclear Information System (INIS)

Velarde, G.; Ahnert, C.; Aragones, J.M.; Leira, G; Martinez-Val, J.M.

1980-01-01

The energy crisis and the need of the nuclear fusion energy are analized. The nuclear processes in the laser interation with the ablator material are studied, as well as the thermohydrodinamic processes in the implossion, and the neutronics of the fusion. The fusion reactor components are described and the economic and social impact of its introduction in the future energetic strategies.(author)

Microencapsulation and fabrication of fuel pellets for inertial confinement fusion

International Nuclear Information System (INIS)

Nolen, R.L. Jr.; Kool, L.B.

1981-01-01

Various microencapsulation techniques were evaluated for fabrication of thermonuclear fuel pellets for use in existing experimental facilities studying inertial confinement fusion and in future fusion-power reactors. Coacervation, spray drying, in situ polymerization, and physical microencapsulation methods were employed. Highly spherical, hollow polymeric shells were fabricated ranging in size from 20 to 7000 micron. In situ polymerization microencapsulation with poly(methyl methacrylate) provided large shells, but problems with local wall defects still must be solved. Extension to other polymeric systems met with limited success. Requirements for inertial confinement fusion targets are described, as are the methods that were used

Computer simulation of charged fusion-product trajectories and detection efficiency expected for future experiments within the COMPASS tokamak

International Nuclear Information System (INIS)

Kwiatkowski, Roch; Malinowski, Karol; Sadowski, Marek J

2014-01-01

This paper presents results of computer simulations of charged particle motions and detection efficiencies for an ion-pinhole camera of a new diagnostic system to be used in future COMPASS tokamak experiments. A probe equipped with a nuclear track detector can deliver information about charged products of fusion reactions. The calculations were performed with a so-called Gourdon code, based on a single-particle model and toroidal symmetry. There were computed trajectories of fast ions (> 500 keV) in medium-dense plasma (n e  < 10 14  cm −3 ) and an expected detection efficiency (a ratio of the number of detected particles to that of particles emitted from plasma). The simulations showed that charged fusion products can reach the new diagnostic probe, and the expected detection efficiency can reach 2 × 10 −8 . Based on such calculations, one can determine the optimal position and orientation of the probe. The obtained results are of importance for the interpretation of fusion-product images to be recorded in future COMPASS experiments. (paper)

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)

Assessment of fusion reactor development. Proceedings

International Nuclear Information System (INIS)

Inoue, N.; Tazima, T.

1994-04-01

Symposium on assessment of fusion reactor development was held to make clear critical issues, which should be resolved for the commercial fusion reactor as a major energy source in the next century. Discussing items were as follows. (1) The motive force of fusion power development from viewpoints of future energy demand, energy resources and earth environment for 'Sustainable Development'. (2) Comparison of characteristics with other alternative energy sources, i.e. fission power and solar cell power. (3) Future planning of fusion research and advanced fuel fusion (D 3 He). (4) Critical issues of fusion reactor development such as Li extraction from the sea water, structural material and safety. (author)

Nuclear fusion: technology development and achievements

International Nuclear Information System (INIS)

Ana, G.; Brad, S.; Lazar, A.; Spiridon, I.; Vijulie, M.

2009-01-01

The strategy for reducing the enhanced greenhouse effect, affecting our planet and the increasing energy demand caused by global growth of population, as well, is, certainly, that of adopting, all the three long-term carbon-free options for energy: renewable sources, fission and fusion reactions. All of them should be further explored and developed for the welfare of future generations, thus leaving them the option of a clean and green energy. From all those available options, the fusion is viewed as an energy source that would be effective in solving future demands, referring to the amount of the energy that can be produced taking into account spent fuel to obtain it. The slow (but steady) progress of fusion development linked with the need for large and expensive experimental devices is remarkable; all available technical and scientific information from experiment shows that progress is being made towards a successful reactor (ITER). The desired objective of this intensive research is obtaining of an industrial reactor able to cover energy future requirements. For the construction of this desired reactor, special designs systems are required. The TRF (TRITIUM RECOVERY FACILITY) is one of the installations that have a major importance maintaining an efficient fuel cycle of the reactor in proper function stage. A test model of TRF for implementation in reactor systems, proposed and developed at ICIT Ramnicu Valcea is presented. (authors)

Status of fusion technology development in JAERI stressing steady-state operation for future reactors

International Nuclear Information System (INIS)

Matsuda, Shinzaburo

2000-01-01

This paper reports on the progress of the fusion reactor technologies developed at the Japan Atomic Energy Research Institute (JAERI) and expected to lead to a future steady state operation reactor. In particular, superconducting coil technology for plasma confinement, NBI and RF systems technology for plasma control and current drive, fueling and pumping systems technology for particle control, heat removal technology, and development of long life materials are highlighted as the important key elements for the future steady state operation. It will be discussed how these key technologies have already been developed by the ITER (International Thermonuclear Experimental Reactor) technology R and D as well as by the Japanese domestic program, and which technologies are planned for the near future

The impact of physics assumptions on fusion economics

International Nuclear Information System (INIS)

Ward, D.; Cook, I.; Knight, P.J.

2001-01-01

The development of fusion promises a long term supply of energy with widespread resources and good safety and environmental properties. However the introduction of fusion into the future energy market will rely on the development of an economically viable fusion power plant. Although predictions of the likely cost of electricity produced by a future fusion power plant are uncertain, it is important that an assessment is made to ensure that the likely economics are not unreasonable. In this paper the impact of different physics (and other) constraints on the economics of fusion is considered. Comparison with the expected future cost of electricity from other sources must take account of the trends in the energy market, particularly at present towards sources with low external costs related to impact on human health and the natural environment. Although these costs depend on the country concerned, a range of expected future costs can be derived. Comparison with the expected range of fusion costs shows that fusion can contribute to the future energy market. (author)

Laser fusion and precision engineering

International Nuclear Information System (INIS)

Nakai, Sadao

1989-01-01

The development of laser nuclear fusion energy for attaining the self supply of energy in Japan and establishing the future perspective as the nation is based in the wide fields of high level science and technology. Therefore to its promotion, large expectation is placed as the powerful traction for the development of creative science and technology which are particularly necessary in Japan. The research on laser nuclear fusion advances steadily in the elucidation of the physics of pellet implosion which is its basic concept and compressed plasma parameters. In September, 1986, the number of neutron generation 10 13 , and in October, 1988, the high density compression 600 times as high as solid density have been achieved. Based on these results, now the laser nuclear fusion is in the situation to begin the attainment of ignition condition for nuclear fusion and the realization of break even. The optical components, high power laser technology, fuel pellet production, high resolution measurement, the simulation of implosion using a supercomputer and so on are closely related to precision engineering. In this report, the mechanism of laser nuclear fusion, the present status of its research, and the basic technologies and precision engineering are described. (K.I.)

Large power supply facilities for fusion research

International Nuclear Information System (INIS)

Miyahara, Akira; Yamamoto, Mitsuyoshi.

1976-01-01

The authors had opportunities to manufacture and to operate two power supply facilities, that is, 125MVA computer controlled AC generator with a fly wheel for JIPP-T-2 stellerator in Institute of Plasma Physics, Nagoya University and 3MW trial superconductive homopolar DC generator to the Japan Society for Promotion of Machine Industry. The 125MVA fly-wheel generator can feed both 60MW (6kV x 10kA) DC power for toroidal coils and 20MW (0.5kV x 40kA) DC power for helical coils. The characteristic features are possibility of Bung-Bung control based on Pontrjagin's maximum principle, constant current control or constant voltage control for load coils, and cpu control for routine operation. The 3MW (150V-20000A) homopolar generator is the largest in the world as superconductive one, however, this capacity is not enough for nuclear fusion research. The problems of power supply facilities for large Tokamak devices are discussed

Charged particle accelerators for inertial fusion energy

International Nuclear Information System (INIS)

Humphries, S. Jr.

1991-01-01

The long history of successful commercial applications of charged-particle accelerators is largely a result of initiative by private industry. The Department of Energy views accelerators mainly as support equipment for particle physicists rather than components of an energy generation program. In FY 91, the DOE spent over 850 M$ on building and supporting accelerators for physics research versus 5 M$ on induction accelerators for fusion energy. The author believes this emphasis is skewed. One must address problems of long-term energy sources to preserve the possibility of basic research by future generations. In this paper, the author reviews the rationale for accelerators as inertial fusion drivers, emphasizing that these devices provide a viable path of fusion energy from viewpoints of both physics and engineering. In this paper, he covered the full range of accelerator fusion applications. Because of space limitations, this paper concentrates on induction linacs for ICF, an approach singled out in recent reports by the National Academy of Sciences and the Fusion Policy Advisory Committee as a promising path to long-term fusion power production. Review papers by Cook, Leung, Franzke, Hofmann and Reiser in these proceedings give details on light ion fusion and RF accelerator studies

Advanced fuels for nuclear fusion reactors

International Nuclear Information System (INIS)

McNally, J.R. Jr.

1974-01-01

Should magnetic confinement of hot plasma prove satisfactory at high β (16 πnkT//sub B 2 / greater than 0.1), thermonuclear fusion fuels other than D.T may be contemplated for future fusion reactors. The prospect of the advanced fusion fuels D.D and 6 Li.D for fusion reactors is quite promising provided the system is large, well reflected and possesses a high β. The first generation reactions produce the very active, energy-rich fuels t and 3 He which exhibit a high burnup probability in very hot plasmas. Steady state burning of D.D can ensue in a 60 kG field, 5 m reactor for β approximately 0.2 and reflectivity R/sub mu/ = 0.9 provided the confinement time is about 38 sec. The feasibility of steady state burning of 6 Li.D has not yet been demonstrated but many important features of such systems still need to be incorporated in the reactivity code. In particular, there is a need for new and improved nuclear cross section data for over 80 reaction possibilities

Computer applications in controlled fusion research

International Nuclear Information System (INIS)

Killeen, J.

1975-01-01

The application of computers to controlled thermonuclear research (CTR) is essential. In the near future the use of computers in the numerical modeling of fusion systems should increase substantially. A recent panel has identified five categories of computational models to study the physics of magnetically confined plasmas. A comparable number of types of models for engineering studies is called for. The development and application of computer codes to implement these models is a vital step in reaching the goal of fusion power. To meet the needs of the fusion program the National CTR Computer Center has been established at the Lawrence Livermore Laboratory. A large central computing facility is linked to smaller computing centers at each of the major CTR Laboratories by a communication network. The crucial element needed for success is trained personnel. The number of people with knowledge of plasma science and engineering trained in numerical methods and computer science must be increased substantially in the next few years. Nuclear engineering departments should encourage students to enter this field and provide the necessary courses and research programs in fusion computing

Fusion safety regulations in the United States: Progress and trends

International Nuclear Information System (INIS)

DeLooper, J.

1994-01-01

This paper explores the issue of regulations as they apply to current and future fusion experimental machines. It addresses fusion regulatory issues, current regulations used for fusion, the Tokamak Fusion Test Reactor experience with regulations, and future regulations to achieve fusion's safety and environmental potential

High stability space frame for a large fusion laser

International Nuclear Information System (INIS)

Hurley, C.A.; Myall, J.O.

1975-01-01

The Shiva laser system is a large neodymium glass laser target irradiation facility being constructed at LLL to perform laser fusion experiments. A frame is being constructed to support the large number of laser components that make up the Shiva system. Twenty laser chains composed of amplifiers, spatial filters, polarizers, rotators, and mirrors will be arranged in an optimum geometry so that each beam arrives at the target simultaneously and within alignment tolerances. This frame is capable of supporting approximately 600 individual component assemblies and maintaining a tolerance of +-4-μrad rotation between any two points over a period of 100 s. Consideration has been given to the positional stability and support of the components, the geometrical array of stacked beams with respect to the oscillator and target, the flow of utilities (e.g., power cables and cooling gas pipes), good accessibility for operation and maintenance, and adaptability for change and growth

Case for the fusion hybrid

International Nuclear Information System (INIS)

Rose, R.P.

1981-01-01

The use of nuclear fusion to produce fuel for nuclear fission power stations is discussed in the context of a crucial need for future energy options. The fusion hybrid is first considered as an element in the future of nuclear fission power to provide long term assurance of adequate fuel supplies for both breeder and convertor reactors. Generic differences in neutronic characteristics lead to a fuel production potential of fusion-fission hybrid systems which is significantly greater than that obtainable with fission systems alone. Furthermore, cost benefit studies show a variety of scenarios in which the hybrid offers sufficient potential to justify development costs ranging in the tens of billions of dollars. The hybrid is then considered as an element in the ultimate development of fusion electric power. The hybrid offers a near term application of fusion where experience with the requisite technologies can be derived as a vital step in mapping a credible route to eventual commercial feasibility of pure fusion systems. Finally, the criteria for assessment of future energy options are discussed with prime emphasis on the need for rational comparision of alternatives

Environmental life cycle assessment of high temperature nuclear fission and fusion biomass gasification plants

International Nuclear Information System (INIS)

Takeda, Shutaro; Sakurai, Shigeki; Kasada, Ryuta; Konishi, Satoshi

2017-01-01

The authors propose nuclear biomass gasification plant as an advancement of conventional gasification plants. Environmental impacts of both fission and fusion plants were assessed through life cycle assessment. The result suggested the reduction of green-house gas emissions would be as large as 85.9% from conventional plants, showing a potential for the sustainable future for both fission and fusion plants. (author)

Data fusion mathematics theory and practice

CERN Document Server

Raol, Jitendra R

2015-01-01

Fills the Existing Gap of Mathematics for Data FusionData fusion (DF) combines large amounts of information from a variety of sources and fuses this data algorithmically, logically and, if required intelligently, using artificial intelligence (AI). Also, known as sensor data fusion (SDF), the DF fusion system is an important component for use in various applications that include the monitoring of vehicles, aerospace systems, large-scale structures, and large industrial automation plants. Data Fusion Mathematics: Theory and Practice offers a comprehensive overview of data fusion, and provides a

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)....

Large area imaging of hydrogenous materials using fast neutrons from a DD fusion generator

Energy Technology Data Exchange (ETDEWEB)

Cremer, J.T., E-mail: ted@adelphitech.com [Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, California 94063 (United States); Williams, D.L.; Gary, C.K.; Piestrup, M.A.; Faber, D.R.; Fuller, M.J.; Vainionpaa, J.H.; Apodaca, M. [Adelphi Technology Inc., 2003 East Bayshore Road, Redwood City, California 94063 (United States); Pantell, R.H.; Feinstein, J. [Department of Electrical Engineering, Stanford University, Stanford, California 94305 (United States)

2012-05-21

A small-laboratory fast-neutron generator and a large area detector were used to image hydrogen-bearing materials. The overall image resolution of 2.5 mm was determined by a knife-edge measurement. Contact images of objects were obtained in 5-50 min exposures by placing them close to a plastic scintillator at distances of 1.5 to 3.2 m from the neutron source. The generator produces 10{sup 9} n/s from the DD fusion reaction at a small target. The combination of the DD-fusion generator and electronic camera permits both small laboratory and field-portable imaging of hydrogen-rich materials embedded in high density materials.

Inertial fusion commercial power plants

International Nuclear Information System (INIS)

Logan, B.G.

1994-01-01

This presentation discusses the motivation for inertial fusion energy, a brief synopsis of five recently-completed inertial fusion power plant designs, some general conclusions drawn from these studies, and an example of an IFE hydrogen synfuel plant to suggest that future fusion studies consider broadening fusion use to low-emission fuels production as well as electricity

Inertial thermonuclear fusion by laser

International Nuclear Information System (INIS)

Watteau, J.P.

1993-12-01

The principles of deuterium tritium (DT) magnetic or inertial thermonuclear fusion are given. Even if results would be better with heavy ions beams, most of the results on fusion are obtained with laser beams. Technical and theoretical aspects of the laser fusion are presented with an extrapolation to the future fusion reactor. (A.B.). 34 refs., 17 figs

Impact of fusion-fission hybrids on world nuclear future

International Nuclear Information System (INIS)

Abdel-Khalick, S.; Jansen, P.; Kessler, G.; Klumpp, P.

1980-08-01

An investigation has been conducted to examine the impact of fusion-fission hybrids on world nuclear future. The primary objectives of this investigation have been: (1) to determine whether hybrids can allow us to meet the projected nuclear component of the world energy demand within current estimates of uranium resources without fast breeders, and (2) to identify the preferred hybrid concept from a resource standpoint. The results indicate that hybrids have the potential to lower the world uranium demand to values well below the resource base. However, the time window for hybrid introduction is quite near and narrow (2000-2020). If historical market penetration rates are assumed, the demand will not be met within the resource base unless hybrids are coupled to the breeders. The results also indicate that from a resource standpoint hybrids which breed their own tritium and have a low blanket energy multiplication are preferable. (orig.) [de

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

International Nuclear Information System (INIS)

Reyes, Susana; Anklam, Tom; Meier, Wayne; Campbell, Patrick; Babineau, Dave; Becnel, James; Taylor, Craig; Coons, Jim

2016-01-01

licensing activities, and summarize our most recent thoughts on safety and tritium considerations for future nuclear fusion facilities.

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

Energy Technology Data Exchange (ETDEWEB)

Reyes, Susana, E-mail: reyes20@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA (United States); Anklam, Tom; Meier, Wayne; Campbell, Patrick [Lawrence Livermore National Laboratory, Livermore, CA (United States); Babineau, Dave; Becnel, James [Savannah River National Laboratory, Aiken, SC (United States); Taylor, Craig; Coons, Jim [Los Alamos National Laboratory, Los Alamos, NM (United States)

2016-11-01

licensing activities, and summarize our most recent thoughts on safety and tritium considerations for future nuclear fusion facilities.

State of the art of fusion material recycling and remaining issues

International Nuclear Information System (INIS)

Massaut, V.; Broden, K.; Pace, L. Di; Ooms, L.; Pampin, R.

2006-01-01

Fusion as a power production system presents several advantages in terms of safety and environmental impact, one of these being the limited amount of radioactive waste production which is burden for future generations. Nevertheless, even if fusion does not produce long term radioactive waste, e.g. by adequate material selection for plasma facing components, there are two important aspects deserving consideration: the presence of tritium in relatively large quantity, and the very hard neutron spectrum leading to large amounts of active materials. In order to keep radioactive waste levels to a minimum it has been proposed to recycle the materials removed from the reactor, after adequate decay period and proper handling and treatment. Treatment may include detritiation, separation of different material types and sorting of the non reusable materials, among others. Moreover if recycle or reuse (within the nuclear industry in general or, for some particular materials, within the fusion industry) are foreseen, the material has to be melted or reduced to reusable raw material, machined or the pieces fabricated again, assembled and checked (for geometrical correctness, or leak tightness for instance). And all this has to be made on industrial scale, as fusion will produce large amounts of material presenting various degrees of radioactivity and tritium content. Even if some experience of recycling exists in the nuclear fission industry, which can be used for fusion materials, the different steps mentioned above are challenging operations when dealing with tritiated materials or highly radioactive components. The paper presents a review of the current situation and state-of-the-art recycling methods for typical fusion materials (e.g. Beryllium, Tungsten, Copper and Copper alloys, steel, Carbon) and components of future fusion plants based on current conceptual design studies. It also focuses attention on R-and-D issues to be addressed in order to be able to recycle as much

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.

Inertial confinement fusion: present status and future potential

International Nuclear Information System (INIS)

Hogan, W.J.

1984-01-01

Power from inertial confinement fusion holds much promise for society. This paper points out many of the benefits relative to combustion of hydrocarbon fuels and fission power. Potential problems are also identified and put in perspective. The progress toward achieving inertial fusion power is described and results of recent work at the Lawrence Livermore National Laboratory are presented. Key phenomenological uncertainties are described and experimental goals for the Nova laser system are given. Several ICF reactor designs 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.)

The European fusion nuclear technology effort

International Nuclear Information System (INIS)

Darvas, J.

1989-01-01

The role of fusion technology in the European fusion development strategy is outlined. The main thrust of the present fusion technology programme is responding to development needs of the Next European Torus. A smaller, but important and growing R and D effort is dealing with problems specific to the Demonstration, or Fusion Power, Reactor. The part of the programme falling under the somewhat arbitrarily defined category of 'fusion nuclear technology' is reviewed and an outlook to future activities is given. The review includes tritium technology, blanket technology and breeder materials development, technology and materials for the protection of the first wall and of other plasma facing components, remote handling technology, and safety and environmental impact studies. A few reflections are offered on the future long-term developments in fusion technology. (orig.)

Control and data management for a large fusion laser

International Nuclear Information System (INIS)

Davis, J.W.; Holloway, F.W.

1975-01-01

SHIVA is a powerful (10-kJ 25 TW) neodymium glass laser system to be used (in 1977) for target irradiation in fusion research. SHIVA is also a development project in that it is pushing the state of the art in laser and optical technology. The present design calls for 20 parallel laser amplification chains whose light output is pointed and focused at a small (100 μ) target within a chamber from semi-equally spaced three-dimensional directions. It is probable that SHIVA will be upgraded to as many as 42 chains in the next few years. Each chain of SHIVA contains 7 high energy laser amplifiers and perhaps 20 other major optical components, many of which send and receive control and measurement information. Again future expansion may add additional elements. Each chain has also associated 10 gimbal or translation motions for beam assignment from the oscillator onto the target

Inertial fusion with hypervelocity impact

International Nuclear Information System (INIS)

Olariu, S.

1998-01-01

The physics of the compression and ignition processes in inertial fusion is to a certain extent independent of the nature of the incident energy pulse. The present strategy in the field of inertial fusion is to study several alternatives of deposition of the incident energy, and, at the same time, of conducting studies with the aid of available incident laser pulses. In a future reactor based on inertial fusion, the laser beams may be replaced by ion beams, which have a better energy efficiency. The main projects in the field of inertial fusion are the National Ignition Facility (NIF) in USA, Laser Megajoule (LMJ) in France, Gekko XII in Japan and Iskra V in Russia. NIF will be constructed at Lawrence Livermore National Laboratory, in California. LMJ will be constructed near Bordeaux. In the conventional approach to inertial confinement fusion, both the high-density fuel mass and the hot central spot are supposed to be produced by the deposition of the driver energy in the outer layers of the fuel capsule. Alternatively, the driver energy could be used only to produce the radial compression of the fuel capsule to high densities but relatively low temperatures, while the ignition of fusion reactions in the compressed capsule should be effected by a synchronized hypervelocity impact. Using this arrangement, it was supposed that a 54 μm projectile is incident with a velocity of 3 x 10 6 m s -1 upon a large-yield deuterium-tritium target at rest. The collision of the incident projectile and of the large-yield target takes place inside a high-Z cavity. A laser or heavy-ion pulse is converted at the walls of the cavity into X-rays, which compresses the incident projectile and the large-yield target in high-density states. The laser pulse and the movement of the incident projectile are synchronized such that the collision should take place when the densities are the largest. The collision converts the kinetic energy of the incident projectile into thermal energy, the

Off-axis multipass amplifier as a large aperture driver stage for fusion lasers

International Nuclear Information System (INIS)

Murray, J.E.; Downs, D.C.; Junt, J.T.; Hermes, G.L.; Warren, W.E.

1981-01-01

A multipass amplifier configuration is described which has potential as a large aperture, high gain driver stage for fusion laser systems. We avoid the present limitations of large aperture switches by using an off-angle geometry that does not require an optical switch. The saturated gain characteristics of this multipass amplifier are optimized numerically. Three potential problems are investigated experimentally, self-lasing, output beam quality, and amplified spontaneous emission output. The results indicate comparable cost for comparable performance to a linear chain, with some operational advantage for the multipass driver stage

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.

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.

User's perspective on fusion

International Nuclear Information System (INIS)

Ashworth, C.P.

1976-01-01

The need in fusion, from the electric utilities viewpoint, is for fusion to be a real option, not huge, complicated nuclear plants costing $10 billion each and requiring restructuring the energy industry to provide and use them. A course for future fusion reactor work in order to be a real option is discussed. The advantages of alternate concepts to the tokamak are presented

Computer applications in controlled fusion research

International Nuclear Information System (INIS)

Killeen, J.

1975-02-01

The role of Nuclear Engineering Education in the application of computers to controlled fusion research can be a very important one. In the near future the use of computers in the numerical modelling of fusion systems should increase substantially. A recent study group has identified five categories of computational models to study the physics of magnetically confined plasmas. A comparable number of types of models for engineering studies are called for. The development and application of computer codes to implement these models is a vital step in reaching the goal of fusion power. In order to meet the needs of the fusion program the National CTR Computer Center has been established at the Lawrence Livermore Laboratory. A large central computing facility is linked to smaller computing centers at each of the major CTR laboratories by a communications network. The crucial element that is needed for success is trained personnel. The number of people with knowledge of plasma science and engineering that are trained in numerical methods and computer science is quite small, and must be increased substantially in the next few years. Nuclear Engineering departments should encourage students to enter this field and provide the necessary courses and research programs in fusion computing. (U.S.)

Materials for fusion reactors

International Nuclear Information System (INIS)

Ehrlich, K.; Kaletta, D.

1978-03-01

The following report describes five papers which were given during the IMF seminar series summer 1977. The purpose of this series was to discuss especially the irradiation behaviour of materials intended for the first wall of future fusion reactors. The first paper deals with the basic understanding of plasma physics relating to the fusion reactor and presents the current state of art of fusion technology. The next two talks discuss the metals intended for the first wall and structural components of a fusion reactor. Since 14 MeV neutrons play an important part in the process of irradiation damage their role is discussed in detail. The question which machines are presently available to simulate irradiation damage under conditions similar to the ones found in a fusion reactor are investigated in the fourth talk which also presents the limitations of the different methods of simulation. In this context also discussed is the importance future intensive neutron sources and materials test reactors will have for this problem area. The closing paper has as a theme the review of the present status of research of metallic and non-metallic materials in view of the quite different requirements for different fusion systems; a closing topic is the world supply on rare materials required for fusion reactors. (orig) [de

New approaches to the economic evaluation of fusion research

International Nuclear Information System (INIS)

Hazelrigg, G.A.; Lietzke, K.R.

1978-01-01

The economic evaluation of fusion research to date has focussed on the benefits of essentially unlimited energy for future generations. In this paper it is shown that energy research in general, and fusion research in particular, also provides benefits in the short term, benefitting us today as well as future generations. Short-term benefits are the result of two distinct aspects of fusion research. First, fusion research provides information for decision making on both the continuing fusion research efforts and on other energy research programs. Second, fusion research provides an expectation of a future energy source thereby promoting accelerated consumption of existing fossil fuels today. Both short-term benefits can be quantitatively evaluated and both are quite substantial. Together, these short-term benefits form the primary economic rationale for fusion research

Impact of fusion-fission hybrids on world nuclear future

International Nuclear Information System (INIS)

Abdel-Khalik, S.I.; Jansen, P.; Kessler, G.; Klumpp, P.

1981-01-01

An investigation has been conducted to examine the impact of fusion-fission hybrids on world nuclear future. The primary objectives of this investigation have been: (1) to determine whether hybrids can allow us to meet the projected nuclear component of the world energy demand within current estimates of uranium resources with or without fast breeders, and (2) to identify the preferred hybrid concept from a resource standpoint. The results indicate that hybrids have the potential to lower the world uranium demand to values well below the resource base. However, the time window for hybrid introduction is quite near and narrow (2000-2020). If historical market penetration rates are assumed, the demand will not be met within the resource base unless hybrids are coupled to the breeders. The results also indicate that from a resource standpoint hybrids which breed their own tritium and have a low blanket energy multiplication are preferable. (orig.) [de

Impact of fusion-fission hybrids on world nuclear future

International Nuclear Information System (INIS)

Abdel-Khalik, S.I.

1980-01-01

An investigation has been conducted to examine the impact of fusion-fission hybrids on world nuclear future. The primary objectives of this investigation have been (1) to determine whether hybrids can allow us to meet the projected nuclear component of the world energy demand within current estimates of uranium resources with or without fast breeders, and (2) to identify the preferred hybrid concept from a resource standpoint. The results indicate that hybrids have the potential to lower the world uranium demand to values well below the resource base. However, the time window for hybrid introduction is quite near and narrow (2000-2020). If historical market penetration rates are assumed, the demand will not be met within the resource base unless hybrides are coupled to the breeders. The results also indicate that from a resource standpaint hybrids which breed their own tritium and have a low blanket energy multiplication are preferable. (orig.) [de

Thermonuclear fusion power

Energy Technology Data Exchange (ETDEWEB)

Lehnert, B

1977-01-01

The present state and future possibilities of controlled-nuclear-fusion research are reviewed, including basic concepts and problems, as well as various approaches based on magnetic- and nonmagnetic-confinement schemes. Considerable progress has so far been made in both plasma physics and fusion-reactor technology, and a closer relationship has been established between theory and experiments. Still, none of the present approaches will, for certain, lead to the final solution of a full-scale reactor. Intensified work along broad lines, with emphasis also on basic research and new ideas, is necessary for future success.

Spin-off produced by the fusion research and development

International Nuclear Information System (INIS)

Koizumi, Koichi; Konishi, T.; Tsuji, Hiroshi

2001-03-01

Nuclear fusion devices are constructed by the integration of many frontier technologies and fusion science based on a wide area of science such as physics, electromagnetics, thermodynamics, mechanics, electrical engineering, electronics, material engineering, heat transfer and heat flow, thermal engineering, neutronics, cryogenics, chemical engineering, control engineering, instrumentation engineering, vacuum engineering. For this, the research and development of elementary technology for fusion devices contributes to advance the technology level of each basic field. In addition, the mutual stimulus among various research fields contributes to increase the potential level of whole 'science and technology'. The spin-offs produced by the fusion technology development give much contribution not only to the general industrial technologies such as semiconductor technology, precision machining of large component, but also contribute to the progress of the accelerator technology, application technology of superconductivity, instrumentation and diagnostics, plasma application technology, heat-resistant and heavy radiation-resistant material technology, vacuum technology, and computer simulation technology. The spin-off produced by the fusion technology development expedite the development of frontier technology of other field and give much contribution to the progress of basic science on physics, space science, material science, medical science, communication, and environment. This report describes the current status of the spin-off effects of fusion research and development by focusing on the contribution of technology development for International Thermonuclear Experimental Reactor (ITER) to industrial technology. The possibilities of future application in the future are also included in this report from the view point of researchers working for nuclear fusion development. Although the nuclear fusion research has a characteristic to integrate the frontier technologies of

Technology issues for decommissioning the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Spampinato, P.T.; Walton, G.R.

1994-01-01

The approach for decommissioning the Tokamak Fusion Test Reactor has evolved from a conservative plan based on cutting up and burying all of the systems, to one that considers the impact tritium contamination will have on waste disposal, how large size components may be used as their own shipping containers, and even the possibility of recycling the materials of components such as the toroidal field coils and the tokamak structure. In addition, the project is more carefully assessing the requirements for using remotely operated equipment. Finally, valuable cost database is being developed for future use by the fusion community

Controlled thermonuclear fusion

CERN Document Server

Bobin, Jean Louis

2014-01-01

The book is a presentation of the basic principles and main achievements in the field of nuclear fusion. It encompasses both magnetic and inertial confinements plus a few exotic mechanisms for nuclear fusion. The state-of-the-art regarding thermonuclear reactions, hot plasmas, tokamaks, laser-driven compression and future reactors is given.

Considerations for tritium protection at a fusion reactor

International Nuclear Information System (INIS)

Easterly, C.E.

1982-01-01

The view on the radiological hazard associated with future fusion power stations as presented in this discussion is rarely supported by reasonably certain or reliably accurate prediction. This fact should not be taken as indicating a major programmatic deficiency. In fact, it is expected that large uncertainty would be present in health effect at the current level of technological development. The details of tritium exposure will be clarified, waiting for the operation of the Tritium System Test Assembly. Once the data base for the TSTA is established, future fusion design can be made based on economic cost/radiation exposure risk benefit. The actual execution of this cost/benefit analysis is complex because three populations are of interest: occupational work force, local population and global population. The knowledge of tritium management must be increased if D-T fusion reactors are to become compatible with the needs of utility companies. In order to exploit the differing hazard between HT and HTO, it is necessary to know much more about the mechanism of uncatalyzed conversion over a wide range of concentration and about the change caused by the variety of potential catalytic sequence in potential tritium leak. (Kako, I.)

Engineering design of a fusion test reactor (FTR) and fusion engineering research facility (FERF) based on a toroidal theta pinch

International Nuclear Information System (INIS)

Abdou, M.; Burke, R.J.; Dauzvardis, P.V.; Foss, M.; Gerstl, S.A.W.; Maroni, V.A.; Pierce, A.W.; Turner, A.F.; Krakowski, R.A.; Linford, R.K.; Oliphant, T.A.; Ribe, F.L.; Thomassen, K.I.

1975-01-01

This paper describes two advanced toroidal theta-pinch devices which are being proposed for future construction. The Fusion Test Reactor (FTR) is being designed to produce thermonuclear energy (at 20 MeV/neutron) equal to the maximum plasma energy (Q=1) and to demonstrate α-particle heating. The Fusion Engineering and Research Facility (FERF) is being designed to test materials in a fusion environment where the average 14-MeV neutron flux from the plasma is greater than or of the order of 5.10 13 n/cm 2 .s over large surface areas. These devices employ the staged theta-pinch principle where the heating is accomplished by rapid (about 0.1 μs) implosion and expansion followed by a slow compression of the plasma. The rapid implosion injects as much heat as possible at as large a plasma radious as possible so that the plasma remains stable even after further compression. The final compression to ignition requires the transfer of a large amount of magnetic energy which implies a long transfer time (about 1 ms) for realistic voltages in the driving circuit. Throughout the heating and burn cycle the plasma must remain in equilibrium and stable to the dominant MHD-modes. A sufficiently large plasma radius guarantees stability against the m = 1 modes. These equilibrium and stability conditions and the requirements on thermonuclear burn determine the design parameters for either machine. The design parameters must also be consistent with economic limitations and technological feasibility of components. In addition to these requirements, the FERF must provide a steady and reliable source of fusion neutrons. (author)

Progress of laser fusion at Lawrence Livermore Laboratory

Energy Technology Data Exchange (ETDEWEB)

Ahlstrom, H G [California Univ., Livermore (USA). Lawrence Livermore Lab.

1979-01-01

Inertial confinement fusion is the present and future source of energy in our universe. Derivatives, such as solar, geothermal, wind, and biomass are proposed as future substitutes for possible fuel sources. All of these possible sources of energy while they may be considered to be renewable do not fulfill the single most important criteria of being unlimited. Fuel reserves of more than 100 billion years are accepted as 'unlimited'. The understanding of fusion has many 'fathers', Bethe, Teller and many others, it has also has proponents (too many to list) as the world's energy supply. This author hopes that this Program's efforts will contribute positively to the advance to the time when fusion energy will positively contribute to the energy supply for mankind. Controlled fusion is judged by us to be the world's most challenging technological problem. The potential benefit to mankind of an unlimited source of energy and thus a higher standard of living make the acceptance of this challenge worth our while. There are many dedicated scientists working on controlled fusion to make this dream a reality. Magnetic and inertial fusion are in a horse race that must not be allowed to falter or to be cancelled. Fusion is the future of the world and one of these approaches to fusion is vital to our future generations.

Progress of laser fusion at Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1979-01-01

Inertial confinement fusion is the present and future source of energy in our universe. Derivatives, such as solar, geothermal, wind, and biomass are proposed as future substitutes for possible fuel sources. All of these possible sources of energy while they may be considered to be renewable do not fulfill the single most important criteria of being unlimited. Fuel reserves of more than 100 billion years are accepted as 'unlimited'. The understanding of fusion has many 'fathers', Bethe, Teller and many others, it has also has proponents (too many to list) as the world's energy supply. This author hopes that this Program's efforts will contribute positively to the advance to the time when fusion energy will positively contribute to the energy supply for mankind. Controlled fusion is judged by us to be the world's most challenging technological problem. The potential benefit to mankind of an unlimited source of energy and thus a higher standard of living make the acceptance of this challenge worth our while. There are many dedicated scientists working on controlled fusion to make this dream a reality. Magnetic and inertial fusion are in a horse race that must not be allowed to falter or to be cancelled. Fusion is the future of the world and one of these approaches to fusion is vital to our future generations

Fusion Power Deployment

International Nuclear Information System (INIS)

Schmidt, J.A.; Ogden, J.M.

2002-01-01

Fusion power plants could be part of a future portfolio of non-carbon dioxide producing energy supplies such as wind, solar, biomass, advanced fission power, and fossil energy with carbon dioxide sequestration. In this paper, we discuss key issues that could impact fusion energy deployment during the last half of this century. These include geographic issues such as resource availability, scale issues, energy storage requirements, and waste issues. The resource needs and waste production associated with fusion deployment in the U.S. should not pose serious problems. One important feature of fusion power is the fact that a fusion power plant should be locatable within most local or regional electrical distribution systems. For this reason, fusion power plants should not increase the burden of long distance power transmission to our distribution system. In contrast to fusion power, regional factors could play an important role in the deployment of renewable resources such as wind, solar and biomass or fossil energy with CO2 sequestration. We examine the role of these regional factors and their implications for fusion power deployment

Safety analysis of fusion reactors pertaining to nuclear incidents and accidents. Final report

International Nuclear Information System (INIS)

Raeder, J.; Weller, A.; Wolf, R.; Jin, X.; Boccaccini, L.V.; Stieglitz, R.; Carloni, D.; Pistner, C.; Herb, J.

2013-11-01

The BfS gave the projekt partners IPP, KIT, Oeko-Institut e. V., and GRS the order to carry out a literature study on the topic of safety of fusion power plants regarding nuclear incidents and accidents. In the framework of this study the actual status of science and technology of the safety concept of fusion power plants should be determined and the applicability of the nuclear safety regulations hitherto developed for nuclear power plants checked. For future commercial fusion power plants today only conceptional designs exist. The most advanced conceptual study for a future fusion power plant is the European Power Plant Conceptual Study (PPCS) from the year 2005, which is based on the tokamak principle. In this study also fundamental aspects of the safety concept of nuclear fusion are treated. Hereby several different conceptual approaches are discussed, which differ among others also in the lay-out approaches relevant for the safety of a facility like for instance the choice of the breeding concept or the materials for the blanket/divertor structure and the coolants. The safety concept of nuclear fusion is oriented on safety concepts for facilities with radioactive inventory. It is based on the concept of tiered safety levels. In order to check whether for the nuclear fusion a safety concept comparable with the nuclear fission at all is necessary, in a first step it was considered, which consequences are possible at a postulated release o large parts of the radioactive inventory of a fusion power plant. Such a worst-case scenario was compared with a corresponding, postulated release of large parts of the radioactive inventory of a nuclear power plant. As scale hereby served the radiological criterion, at the transgression of which in the environment of the facility an evacuation would be necessary. In a next step the transferability of the safety concept of the tiered safety levels of nuclear technology to the fusion was checked. Beside events transferable from

Review of the safety concept for fusion reactor concepts and transferability of the nuclear fission regulation to potential fusion power plants

Energy Technology Data Exchange (ETDEWEB)

Raeder, Juergen; Weller, Arthur; Wolf, Robert [Max-Planck-Institut fuer Plasmaphysik (IPP), Garching (Germany); Jin, Xue Zhou; Boccaccini, Lorenzo V.; Stieglitz, Robert; Carloni, Dario [Karlsruher Institute fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Pistner, Christoph [Oeko-Institut e.V., Darmstadt (Germany); Herb, Joachim [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

2016-01-15

This paper summarizes the current state of the art in science and technology of the safety concept for future fusion power plants (FPPs) and examines the transferability of the current nuclear fission regulation to the concepts of future fusion power plants. At the moment there exist only conceptual designs of future fusion power plants. The most detailed concepts with regards to safety aspects were found in the European Power Plant Conceptual Study (PPCS). The plant concepts discussed in the PPCS are based on magnetic confinement of the plasma. The safety concept of fusion power plants, which has been developed during the last decades, is based on the safety concepts of installations with radioactive inventories, especially nuclear fission power plants. It applies the concept of defence in depth. However, there are specific differences between the implementations of the safety concepts due to the physical and technological characteristics of fusion and fission. It is analysed whether for fusion a safety concept is required comparable to the one of fission. For this the consequences of a purely hypothetical release of large amounts of the radioactive inventory of a fusion power plant and a fission power plant are compared. In such an event the evacuation criterion outside the plant is exceeded by several orders of magnitude for a fission power plant. For a fusion power plant the expected radiological consequences are of the order of the evacuation criterion. Therefore, a safety concept is also necessary for fusion to guarantee the confinement of the radioactive inventory. The comparison between the safety concepts for fusion and fission shows that the fundamental safety function ''confinement of the radioactive materials'' can be transferred directly in a methodical way. For a fusion power plant this fundamental safety function is based on both, physical barriers as well as on active retention functions. After the termination of the fusion

Target technologies for laser inertial confinement fusion: state-of-the-art and future perspective

International Nuclear Information System (INIS)

Zhang Lin; Du Kai

2013-01-01

Targets are physical base of the laser inertial confinement fusion (ICF) researches. The quality of the targets has extremely important influences on the reliabilities and degree of precision of the ICF experimental results. The characteristics of the ICF targets, such as complexity and microscale, high precision, determine that the target fabrication process must be a system engineering. This paper presents progresses on the fabrication technologies of ICF targets. The existing problem and the future needs of ICF target fabrication technologies are also discussed. (authors)

JET:Preparing the future in fusion

Czech Academy of Sciences Publication Activity Database

Mlynář, Jan; Ongena, J.; Ďuran, Ivan; Hron, Martin; Pánek, Radomír; Petržílka, Václav; Žáček, František

2004-01-01

Roč. 54, suppl.C (2004), C28-C38 ISSN 0011-4626. [Symposium on Plasma Physics and Technology /21st/. Praha, 14.06.2004-17.06.2004] R&D Projects: GA ČR GA202/04/0360 Institutional research plan: CEZ:AV0Z2043910 Keywords : fusion, tokamak, JET EFDA, ITER Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 0.292, year: 2004

Fusion science and technology at CIEMAT; Ciencia y Tecnologia de fusion en el Ciemat

Energy Technology Data Exchange (ETDEWEB)

Sanchez, J.

2012-07-01

The presence of the agency Fusion for Energy and the significant participation of Spanish industry in the ITER project bring Spain to a relevant position in the development of fusion. This article reviews briefly the role of Ciemat in the process leading to this situation and analyzers the scientific and technological role of Ciemat in the present and future phases of the fusion programme. (Author)

Evaluation of fusion study from socio-economic aspects

International Nuclear Information System (INIS)

Konishi, S.; Okano, K.; Ogawa, Y.; Nagumo, S.; Tokimatsu, K.; Tobita, K.

2005-01-01

A fusion research project was evaluated from the aspects of socio-economics and its possible economic benefit. Research project itself has large economic impacts and it appears in a different way in different time. Four categories were identified as such mechanisms; direct economic effect by purchase and employment, the growth of local community and its economy, an improvement of technical capability of the industry stimulated by the development, and fusion energy supply under environmental constraints. Industrial effects were analysed from actual R and D program and found to yield considerable economic outcome, although contribution by the research itself is far smaller than that required for industry before actual commercial products can be produced. Economic value of fusion energy could be huge, but appears several decades future, and should be reduced by discount rate and success probability. Its value is more important as a part of environmental policy. Value of the fusion research at present age cannot be estimated as actual benefit, but as the effectiveness in the policy, or benefit for public that is now regarded as a kind of Externality

The European fusion program and the role of the research reactors

International Nuclear Information System (INIS)

Laesser, R.; Andreani, R.; Diegele, E.

2005-01-01

The main objectives of the European long-term Fusion Technology Program are i) investigation of DEMO breeding blankets options, ii) development of low activation materials resistant to high neutron fluence, iii) construction of IFMIF for validation of DEMO materials, and iv) promotion of modelling efforts for the understanding of radiation damage. A large effort is required for the development and performance verification of the materials subjected to the intense neutron irradiation encountered in fusion reactors. In the absence of a strong 14.1 MeV neutron source fission materials research reactors are used. Elaborate in-pile and post-irradiation examinations are performed. In addition, the modelling effort is increased to predict the damage by a 'true' fusion spectrum in the future. Even assuming that a positive decision for IFMIF construction can be reached, the operation of a limited number of materials test reactors is needed to perform irradiation studies on large samples and for screening. (author)

Possible futures for the development of a fusion demonstration plant

International Nuclear Information System (INIS)

Nichols, S.P.

1976-01-01

As indicated by the Fusion Planning Bulletins, the Division of Controlled Thermonuclear Research is becoming involved in planning with alternative scenarios. The Center for Energy Studies at the University of Texas at Austin has been involved with such planning for several years and has examined various scenarios for fusion power development using the Partitive Analytical Forecasting (PAF) technique. The most recent studies compare the long-term plan presented in WASH-1290, Fusion Power by Magnetic Confinement, with other plans that have been proposed, such as the plan proposed by Kulcinski and Conn of the University of Wisconsin. The study indicates that some of the alternative plans do have possibilities to shorten the required time for the completion of a demonstration fusion plant without increased costs or a decrease in the likelihood of success. The current efforts of the project are in the planning exercises recently completed by committees set up by the DCTR. Further comparisons of alternative scenarios will be performed as part of this effort

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 Sustainable Nuclear Future: Fission and Fusion E.M. Campbell Logos Technologies

Science.gov (United States)

Campbell, E. Michael

2010-02-01

Global industrialization, the concern over rising CO2 levels in the atmosphere and other negative environmental effects due to the burning of hydrocarbon fuels and the need to insulate the cost of energy from fuel price volatility have led to a renewed interest in nuclear power. Many of the plants under construction are similar to the existing light water reactors but incorporate modern engineering and enhanced safety features. These reactors, while mature, safe and reliable sources of electrical power have limited efficiency in converting fission power to useful work, require significant amounts of water, and must deal with the issues of nuclear waste (spent fuel), safety, and weapons proliferation. If nuclear power is to sustain its present share of the world's growing energy needs let alone displace carbon based fuels, more than 1000 reactors will be needed by mid century. For this to occur new reactors that are more efficient, versatile in their energy markets, require minimal or no water, produce less waste and more robust waste forms, are inherently safe and minimize proliferation concerns will be necessary. Graphite moderated, ceramic coated fuel, and He cooled designs are reactors that can satisfy these requirements. Along with other generation IV fast reactors that can further reduce the amounts of spent fuel and extend fuel resources, such a nuclear expansion is possible. Furthermore, facilities either in early operations or under construction should demonstrate the next step in fusion energy development in which energy gain is produced. This demonstration will catalyze fusion energy development and lead to the ultimate development of the next generation of nuclear reactors. In this presentation the role of advanced fission reactors and future fusion reactors in the expansion of nuclear power will be discussed including synergies with the existing worldwide nuclear fleet. )

Laser fusion program overview

International Nuclear Information System (INIS)

Emmett, J.L.

1977-01-01

This program is structured to proceed through a series of well defined fusion milestones to proof of the scientific feasibility, of laser fusion with the Shiva Nova system. Concurrently, those key technical areas, such as advanced lasers, which are required to progress beyond proof of feasibility, are being studied. We have identified and quantified the opportunities and key technical issues in military applications, such as weapons effects simulations, and in civilian applications, such as central-station electric power production. We summarize the current status and future plans for the laser fusion program at LLL, emphasizing the civilian applications of laser fusion

Recycling fusion materials

International Nuclear Information System (INIS)

Ooms, L.

2005-01-01

The inherent safety and environmental advantages of fusion power in comparison with other energy sources play an important role in the public acceptance. No waste burden for future generations is therefore one of the main arguments to decide for fusion power. The waste issue has thus been studied in several documents and the final conclusion of which it is stated that there is no permanent disposal waste needed if recycling is applied. But recycling of fusion reactor materials is far to be obvious regarding mostly the very high specific activity of the materials to be handled, the types of materials and the presence of tritium. The main objective of research performed by SCK-CEN is to study the possible ways of recycling fusion materials and analyse the challenges of the materials management from fusion reactors, based on current practices used in fission reactors and the requirements for the manufacture of fusion equipment

Towards fusion power

International Nuclear Information System (INIS)

Venkataraman, G.

1975-01-01

An attempt has been made to present general but broad review of the recent developments in the field of plasma physics and its application to fusion power. The first chapter describes the fusion reactions and fusion power systems. The second chapter deals in detail with production and behaviour of plasma, screening, oscillations, instability, energy losses, temperature effects, etc. Magnetic confinements, including pinch systems, toroidal systems such as Tokamac and stellarator, minor machine, etc. are discussed in detail in chapter III. Laser produced plasma, laser implosion and problems associated with it and future prospects are explained in chapter IV. Chapter V is devoted entirely to the various aspects of hybrid systems. The last chapter throws light on problems of fusion technology, such as plasma heating, vacuum requirements, radiation damage, choice of materials, blanket problems, hazards of fusion reactions, etc. (K.B.)

Modelling irradiation effects in fusion materials

International Nuclear Information System (INIS)

Victoria, M.; Dudarev, S.; Boutard, J.L.; Diegele, E.; Laesser, R.; Almazouzi, A.; Caturla, M.J.; Fu, C.C.; Kaellne, J.; Malerba, L.; Nordlund, K.; Perlado, M.; Rieth, M.; Samaras, M.; Schaeublin, R.; Singh, B.N.; Willaime, F.

2007-01-01

We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future development. Large-scale density functional theory (DFT) calculations reveal the structure of the point defects in α-Fe, and highlight the crucial part played by magnetism. The calculations give accurate migration energies of point defects and the strength of their interaction with He atoms. Kinetic models based on DFT results reproduce the stages of radiation damage recovery in iron, and stages of He-desorption from pre-implanted iron. Experiments aimed at validating the models will be carried out in the future using a multi-beam ion irradiation facility chosen for its versatility and rapid feedback

Modelling irradiation effects in fusion materials

Energy Technology Data Exchange (ETDEWEB)

Victoria, M. [Instituto de Fusion Nuclear, Universidad Politecnica de Madrid, c/Jose Gutierrez Abascal 2, 28006 Madrid (Spain); Dudarev, S. [EURATOM/UKAEA Fusion Association, Culham Science Centre, Oxfordshire OX14 3DB, UK and Department of Physics, Imperial College, Exhibition Road, London SW7 2AZ (United Kingdom); Boutard, J.L. [EFDA-CSU Garching, Boltzmannstrasse 2, D-85748 Garching (Germany)], E-mail: jean-louis.boutard@tech.efda.org; Diegele, E.; Laesser, R. [EFDA-CSU Garching, Boltzmannstrasse 2, D-85748 Garching (Germany); Almazouzi, A. [Structural Materials Expert Group, Nuclear Materials Science Institute, SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Caturla, M.J. [Departamento de Fisica Aplicada, Universidad de Alicante, 03690 San Vicente de Raspeig (Spain); Fu, C.C. [Service de Metallurgie Physique, CEA/Saclay, F-91191 Gif sur Yvette Cedex (France); Kaellne, J. [Department of Engineering Sciences, Uppsala University, Box 534, S-751 21 Uppsala (Sweden); Malerba, L. [Structural Materials Expert Group, Nuclear Materials Science Institute, SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Nordlund, K. [Association EURATOM-Tekes, Accelerator Laboratory, P.O. Box 43, 00014 University of Helsinki (Finland); Perlado, M. [Instituto de Fusion Nuclear, Universidad Politecnica de Madrid, c/Jose Gutierrez Abascal 2, 28006 Madrid (Spain); Rieth, M. [Forschungszentrum Karlsruhe, Institut fuer Materialforschung I, P.O. Box 3640, D-76021 Karlsruhe (Germany); Samaras, M. [Paul Scherrer Institute, Nuclear Energy and Safety Department, CH-5232 Villigen PSI (Switzerland); Schaeublin, R. [Ecole Polytechnique Federale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas, Association Euratom-Confederation Suisse, CH-5232 Villigen PSI (Switzerland); Singh, B.N. [Department of Materials Research, Risoe National Laboratory, DK-4000 Roskilde (Denmark); Willaime, F. [Service de Metallurgie Physique, CEA/Saclay, F-91191 Gif sur Yvette Cedex (France)

2007-10-15

We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future development. Large-scale density functional theory (DFT) calculations reveal the structure of the point defects in {alpha}-Fe, and highlight the crucial part played by magnetism. The calculations give accurate migration energies of point defects and the strength of their interaction with He atoms. Kinetic models based on DFT results reproduce the stages of radiation damage recovery in iron, and stages of He-desorption from pre-implanted iron. Experiments aimed at validating the models will be carried out in the future using a multi-beam ion irradiation facility chosen for its versatility and rapid feedback.

Tertiary proton diagnostics in future inertial confinement fusion experiments

International Nuclear Information System (INIS)

Cremer, S.; Verdon, C.P.; Petrasso, R.D.

1998-01-01

Recently, it was proposed to use energetic (up to 31 MeV) tertiary protons produced during the final stage of inertial confinement fusion implosions to measure the fuel areal density of compressed deuterium endash tritium (DT). The method is based on seeding the fuel with 3 He. The reaction of 3 He ions with the energetic knock-on deuterons, produced via the elastic scattering of 14.1 MeV neutrons, is a source of very energetic protons capable of escaping from very large areal density targets. This work presents results of detailed time-dependent Monte Carlo simulations of the nuclear processes involved in producing and transporting these protons through imploding targets proposed for direct-drive experiments on OMEGA [D. K. Bradley et al., Phys. Plasmas 5, 1870 (1998)] and the National Ignition Facility [S. W. Haan et al., Phys. Plasmas 2, 2480 (1995)]. copyright 1998 American Institute of Physics

ITER: Fusion research at the dawn of a new era

International Nuclear Information System (INIS)

Aymar, R.

2002-01-01

Given the expected success of on-going negotiations on the Joint Implementing Agreement for ITER construction and operation, a new era is opening in which fusion laboratories will have more dependable external support where they follow programmes supporting fusion as an energy source. The ITER design, cost estimate and safety analysis are supported by a large body of validating physics and technology R and D. The main features of the design, and analysis of its performance, give confidence that it will fulfil its technical objectives and demonstrate the environmental attractiveness of fusion. This paper gives illustrative confirmation of these expectations and an update on the technical preparations for construction, as well as the status of negotiations. These show that ITER is the right next step, integrating the appropriate physics and technology, making the proper technical and financial compromise and being conducted within an international framework, to advance fusion towards the objective of becoming an energy source in the foreseeable future. (author)

Analyzing large data sets from XGC1 magnetic fusion simulations using apache spark

Energy Technology Data Exchange (ETDEWEB)

Churchill, R. Michael [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

2016-11-21

Apache Spark is explored as a tool for analyzing large data sets from the magnetic fusion simulation code XGCI. Implementation details of Apache Spark on the NERSC Edison supercomputer are discussed, including binary file reading, and parameter setup. Here, an unsupervised machine learning algorithm, k-means clustering, is applied to XGCI particle distribution function data, showing that highly turbulent spatial regions do not have common coherent structures, but rather broad, ring-like structures in velocity space.

Neutral-beam systems for magnetic-fusion reactors

International Nuclear Information System (INIS)

Fink, J.H.

1981-01-01

Neutral beams for magnetic fusion reactors are at an early stage of development, and require considerable effort to make them into the large, reliable, and efficient systems needed for future power plants. To optimize their performance to establish specific goals for component development, systematic analysis of the beamlines is essential. Three ion source characteristics are discussed: arc-cathode life, gas efficiency, and beam divergence, and their significance in a high-energy neutral-beam system is evaluated

Identification of future engineering-development needs of alternative concepts for magnetic-fusion energy

International Nuclear Information System (INIS)

Krakowski, R.A.

1982-01-01

A qualitative identification of future engineering needs of alternative fusion concepts (AFCs) is presented. These needs are assessed relative to the similar needs of the tokamak in order to emphasize differences in required technology with respect to the well documented mainline approach. Although nearly thirty AFCs can be identified as being associated with some level of reactor projection, redirection, refocusing, and general similarities can be used to generate a reduced AFC list that includes only the bumpy tori, stellarators, reversed-field pinches, and compact toroids. Furthermore, each AFC has the potential of operating as a conventional (low power density, superconducting magnets) or a compact, high-power-density (HPD) system. Hence, in order to make tractable an otherwise difficult task, the future engineering needs for the AFCs are addressed here for conventional versus compact approaches, with the latter being treated as a generic class and the former being composed of bumpy tori, stellarators, reversed-field pinches, and compact toroids

Coatings for laser fusion

International Nuclear Information System (INIS)

Lowdermilk, W.H.

1981-01-01

Optical coatings are used in lasers systems for fusion research to control beam propagation and reduce surface reflection losses. The performance of coatings is important in the design, reliability, energy output, and cost of the laser systems. Significant developments in coating technology are required for future lasers for fusion research and eventual power reactors

Laser fusion

International Nuclear Information System (INIS)

Ashby, D.E.T.F.

1976-01-01

A short survey is given on laser fusion its basic concepts and problems and the present theoretical and experimental methods. The future research program of the USA in this field is outlined. (WBU) [de

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)

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)

Material Challenges For Plasma Facing Components in Future Fusion Reactors

International Nuclear Information System (INIS)

Linke, J; Pintsuk, G.; Rödig, M.

2013-01-01

Increasing attention is directed towards thermonuclear fusion as a possible future energy source. Major advantages of this energy conversion technology are the almost inexhaustible resources and the option to produce energy without CO2-emissions. However, in the most advanced field of magnetic plasma confinement a number of technological challenges have to be met. In particular high-temperature resistant and plasma compatible materials have to be developed and qualified which are able to withstand the extreme environments in a commercial thermonuclear power reactor. The plasma facing materials (PFMs) and components (PFCs) in such fusion devices, i.e. the first wall (FW), the limiters and the divertor, are strongly affected by the plasma wall interaction processes and the applied intense thermal loads during plasma operation. On the one hand, these mechanisms have a strong influence on the plasma performance; on the other hand, they have major impact on the lifetime of the plasma facing armour. In present-day and next step devices the resulting thermal steady state heat loads to the first wall remain below 1 MWm-2; the limiters and the divertor are expected to be exposed to power densities being at least one order of magnitude above the FW-level, i.e. up to 20 MWm-2 for next step tokamaks such as ITER or DEMO. These requirements are responsible for high demands on the selection of qualified PFMs and heat sink materials as well as reliable fabrication processes for actively cooled plasma facing components. The technical solutions which are considered today are mainly based on the PFMs beryllium, carbon or tungsten joined to copper alloys or stainless steel heat sinks. In addition to the above mentioned quasi-stationary heat loads, short transient thermal pulses with deposited energy densities up to several tens of MJm-2 are a serious concern for next step tokamak devices. The most frequent events are so-called Edge Localized Modes (type I ELMs) and plasma disruptions

The fusion dilemma

International Nuclear Information System (INIS)

Carruthers, R.

1981-01-01

The present position in fusion research is reviewed and discussed with relation to the requirements of an economic reactor. Meeting these requirements calls for a mission-oriented project of interdisciplinary character whose timely evolution from one with a research orientation, is a challenging management problem. The cost-effectiveness of future expenditure on fusion research is dependent upon acknowledging this challenge and realistically facing the difficult tasks which it presents. (U.K.)

ITER and the road map towards fusion energy

International Nuclear Information System (INIS)

Tran, M.Q.

2005-01-01

Outlined is a fusion as a sustainable energy, the conditions and challenges for the realisation of fusion energy. Given is electricity generating power plant conceptual study and the rule of fusion energy in future energy scenarios

Management of nontritium radioactive wastes from fusion power plants

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-09-01

This report identifies nontritium radioactive waste sources for current conceptual fusion reactor designs. Quantities and compositions of the radwaste are estimated for the tokamaks of the University of Wisconsin (UWMAK-I), the Princeton Plasma Physics Laboratory (PPPL), and the Oak Ridge National Laboratory (ORNL); the Reference Theta Pinch Reactor of the Los Alamos Scientific Laboratory (LASL); and the Minimum Activation Blanket of the Brookhaven National Laboratory (BNL). Disposal of large amounts of radioactive waste appears necessary for fusion reactors. Although the curie (Ci) level of the wastes is comparable to that of fission products in fission reactors, the isotopes are less hazardous, and have shorter half-lives. Therefore radioactivity from fusion power production should pose a smaller risk than radioactivity from fission reactors. Radioactive waste sources identified for the five reference plants are summarized. Specific radwaste treatments or systems had to be assumed to estimate these waste quantities. Future fusion power plant conceptual designs should include radwaste treatment system designs so that assumed designs do not have to be used to assess the environmental effects of the radioactive waste

Interim report of working group of Nuclear Fusion Committee

International Nuclear Information System (INIS)

Takuma, Hiroshi

1986-01-01

The conclusion of the working group was presented as an interim report to the general meeting of Nuclear Fusion Committee, which became the base for deciding the future plan. The report was the result of the hard work for about a half year by five Committee experts and 23 researchers, and has the rich contents. At present, the supply of petroleum relaxed, and the trend that a large amount of investment for a long period for nuclear fusion research is problematical has become strong. Of course, the importance of the nuclear fusion research never changes. The research projects of Heliotron E, Gekko 12, Gamma 10 and so on have advanced, and the base for synthetically promoting the research has been completed. It is indispensable to decide the most effective plan for the next stage. The working group discussed on the five year plan, especially on the research based on a large project. The policy of the works and problems, the progress of the works of respective subgroups, and the summarization are reported. The researches on nuclear burning simulation, no current plasma using an external conductor system and making an axisymmetrical high-beta torus steady were proposed. (Kako, I.)

Concepts for Future Large Fire Modeling

Science.gov (United States)

A. P. Dimitrakopoulos; R. E. Martin

1987-01-01

A small number of fires escape initial attack suppression efforts and become large, but their effects are significant and disproportionate. In 1983, of 200,000 wildland fires in the United States, only 4,000 exceeded 100 acres. However, these escaped fires accounted for roughly 95 percent of wildfire-related costs and damages (Pyne, 1984). Thus, future research efforts...

Review of fusion synfuels

International Nuclear Information System (INIS)

Fillo, J.A.

1980-01-01

Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high-temperature electrolysis of approx. 50 to 65% are projected for fusion reactors using high-temperatures blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long term, there could be a gradual transition to an inexhaustible energy system based solely on fusion

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

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

Demountable toroidal fusion core facility for physics optimization and fusion engineering

International Nuclear Information System (INIS)

Bogart, S.L.; Wagner, C.E.; Krall, N.A.; Dalessandro, J.A.; Weggel, C.F.; Lund, K.O.; Sedehi, S.

1986-01-01

Following a successful compact ignition tokamak (CIT) experiment, a fusion facility will be required for physics optimization (POF) and fusion engineering research (FERF). The POF will address issues such as high-beta operation, current drive, impurity control, and will test geometric and configurational variations such as the spherical torus or the reversed-field pinch (RFP). The FERF will be designed to accumulate rapidly a large neutron dose in prototypical fusion subsystems exposed to radiation. Both facilities will require low-cost replacement cores and rapid replacement times. The Demountable Toroidal Fusion Core (DTFC) facility is designed to fulfill these requirements. It would be a cost-effective stepping stone between the CIT and a demonstration fusion reactor

Magnetic Fusion Program Plan

International Nuclear Information System (INIS)

1985-02-01

This Plan reflects the present conditions of the energy situation and is consistent with national priorities for the support of basic and applied research. It is realistic in taking advantage of the technical position that the United States has already established in fusion research to make cost-effective progress toward the development of fusion power as a future energy option

International fusion research council

International Nuclear Information System (INIS)

Belozerov, A.N.

1977-01-01

A brief history of the International Fusion Research Council (IFRC) is given and the minutes of the 1976 meeting in Garching are summarized. At the Garching meeting, the IFRC evaluated the quality of papers presented at recent IAEA conferences on plasma physics and controlled thermonuclear research, and made recommendations on the organization and timing of future meetings on nuclear fusion

Optical Fiber Fusion Splicing

CERN Document Server

Yablon, Andrew D

2005-01-01

This book is an up-to-date treatment of optical fiber fusion splicing incorporating all the recent innovations in the field. It provides a toolbox of general strategies and specific techniques that the reader can apply when optimizing fusion splices between novel fibers. It specifically addresses considerations important for fusion splicing of contemporary specialty fibers including dispersion compensating fiber, erbium-doped gain fiber, polarization maintaining fiber, and microstructured fiber. Finally, it discusses the future of optical fiber fusion splicing including silica and non-silica based optical fibers as well as the trend toward increasing automation. Whilst serving as a self-contained reference work, abundant citations from the technical literature will enable readers to readily locate primary sources.

Stockpile tritium production from fusion

International Nuclear Information System (INIS)

Lokke, W.A.; Fowler, T.K.

1986-01-01

A fusion breeder holds the promise of a new capability - ''dialable'' reserve capacity at little additional cost - that offers stockpile planners a new way to deal with today's uncertainties in forecasting long range needs. Though still in the research stage, fusion can be developed in time to meet future military requirements. Much of the necessary technology will be developed by the ongoing magnetic fusion energy program. However, a specific program to develop the nuclear technology required for materials production is needed if fusion is to become a viable option for a new production complex around the turn of the century

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)

Results from levels 2/3 fusion implementations: issues, challenges, retrospectives, and perspectives for the future an annotated perspective

Science.gov (United States)

Kadar, Ivan; Bosse, Eloi; Salerno, John; Lambert, Dale A.; Das, Subrata; Ruspini, Enrique H.; Rhodes, Bradley J.; Biermann, Joachim

2008-04-01

Even though the definition of the Joint Director of Laboratories (JDL) "fusion levels" were established in 1987, published 1991, revised in 1999 and 2004, the meaning, effects, control and optimization of interactions among the fusion levels have not as yet been fully explored and understood. Specifically, this is apparent from the abstract JDL definitions of "Levels 2/3 Fusion" - situation and threat assessment (SA/TA), which involve deriving relations among entities, e.g., the aggregation of object states (i.e., classification and location) in SA, while TA uses SA products to estimate/predict the impact of actions/interactions effects on situations taken by the participant entities involved. Given all the existing knowledge in the information fusion and human factors literature, (both prior to and after the introduction of "fusion levels" in 1987) there are still open questions remaining in regard to implementation of knowledge representation and reasoning methods under uncertainty to afford SA/TA. Therefore, to promote exchange of ideas and to illuminate the historical, current and future issues associated with Levels 2/3 implementations, leading experts were invited to present their respective views on various facets of this complex problem. This paper is a retrospective annotated view of the invited panel discussion organized by Ivan Kadar (first author), supported by John Salerno, in order to provide both a historical perspective of the evolution of the state-of-the-art (SOA) in higher-level "Levels 2/3" information fusion implementations by looking back over the past ten or more years (before JDL), and based upon the lessons learned to forecast where focus should be placed to further enhance and advance the SOA by addressing key issues and challenges. In order to convey the panel discussion to audiences not present at the panel, annotated position papers summarizing the panel presentation are included.

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

Fusion science and technology at CIEMAT

International Nuclear Information System (INIS)

Sanchez, J.

2012-01-01

The presence of the agency Fusion for Energy and the significant participation of Spanish industry in the ITER project bring Spain to a relevant position in the development of fusion. This article reviews briefly the role of Ciemat in the process leading to this situation and analyzers the scientific and technological role of Ciemat in the present and future phases of the fusion programme. (Author)

Fusion plasma physics

CERN Document Server

Stacey, Weston M

2012-01-01

This revised and enlarged second edition of the popular textbook and reference contains comprehensive treatments of both the established foundations of magnetic fusion plasma physics and of the newly developing areas of active research. It concludes with a look ahead to fusion power reactors of the future. The well-established topics of fusion plasma physics -- basic plasma phenomena, Coulomb scattering, drifts of charged particles in magnetic and electric fields, plasma confinement by magnetic fields, kinetic and fluid collective plasma theories, plasma equilibria and flux surface geometry, plasma waves and instabilities, classical and neoclassical transport, plasma-materials interactions, radiation, etc. -- are fully developed from first principles through to the computational models employed in modern plasma physics. The new and emerging topics of fusion plasma physics research -- fluctuation-driven plasma transport and gyrokinetic/gyrofluid computational methodology, the physics of the divertor, neutral ...

Fusion reactor development using high power particle beams

International Nuclear Information System (INIS)

Ohara, Y.

1990-01-01

The present paper outlines major applications of the ion source/accelerator to fusion research and also addresses the present status and future plans for accelerator development. Applications of ion sources/accelerators for fusion research are discussed first, focusing on plasma heating, plasma current drive, plasma current profile control, and plasma diagnostics. The present status and future plan of ion sources/accelerators development are then described focusing on the features of existing and future tokamak equipment. Positive-ion-based NBI systems of 100 keV class have contributed to obtaining high temperature plasmas whose parameters are close to the fusion break-even condition. For the next tokamak fusion devices, a MeV class high power neutral beam injector, which will be used to obtain a steady state burning plasma, is considered to become the primary heating and current drive system. Development of such a system is a key to realize nuclear fusion reactor. It will be entirely indebted to the development of a MeV class high current negative deuterium ion source/accelerator. (N.K.)

Spatiotemporal Fusion of Multisource Remote Sensing Data: Literature Survey, Taxonomy, Principles, Applications, and Future Directions

Directory of Open Access Journals (Sweden)

Xiaolin Zhu

2018-03-01

Full Text Available Satellite time series with high spatial resolution is critical for monitoring land surface dynamics in heterogeneous landscapes. Although remote sensing technologies have experienced rapid development in recent years, data acquired from a single satellite sensor are often unable to satisfy our demand. As a result, integrated use of data from different sensors has become increasingly popular in the past decade. Many spatiotemporal data fusion methods have been developed to produce synthesized images with both high spatial and temporal resolutions from two types of satellite images, frequent coarse-resolution images, and sparse fine-resolution images. These methods were designed based on different principles and strategies, and therefore show different strengths and limitations. This diversity brings difficulties for users to choose an appropriate method for their specific applications and data sets. To this end, this review paper investigates literature on current spatiotemporal data fusion methods, categorizes existing methods, discusses the principal laws underlying these methods, summarizes their potential applications, and proposes possible directions for future studies in this field.

Development of electrical insulation and conduction coating for fusion experimental devices

Energy Technology Data Exchange (ETDEWEB)

Onozuka, M. [Mitsubishi Heavy Industries Ltd., Yokohama (Japan); Tsujimura, S. [Mitsubishi Heavy Industries Ltd., Yokohama (Japan); Toyoda, M. [Mitsubishi Heavy Industries Ltd., Yokohama (Japan); Inoue, M. [Mitsubishi Heavy Industries Ltd., Yokohama (Japan); Abe, T. [Japan Atomic Energy Research Inst., Naka (Japan); Murakami, Y. [Japan Atomic Energy Research Inst., Naka (Japan)

1995-12-31

Development of electrical insulation and conduction methods that can be applied for large components have been investigated for future large fusion experimental devices. A thermal spraying method is employed to coat the insulation or conduction materials on the structural components. Al{sub 2}O{sub 3} has been selected as an insulation material, while Cr{sub 3}C{sub 2}-NiCr and WC-NiCr have been chosen as conduction materials. These materials were coated on stainless steel base plates to examine the basic characteristics of the coated layers, such as their adhesive strength to the base plate and electrical resistance. It was found that they have sufficient electrical insulation and conduction properties, respectively. In addition, the sliding tests of the coated layers showed sufficient frictional properties. The applicability of the spraying method was examined on a 100mm x 1000mm surface and found to be applicable for large surfaces in fusion experimental devices. (orig.).

Development of electrical insulation and conduction coating for fusion experimental devices

International Nuclear Information System (INIS)

Onozuka, M.; Tsujimura, S.; Toyoda, M.; Inoue, M.; Abe, T.; Murakami, Y.

1995-01-01

Development of electrical insulation and conduction methods that can be applied for large components have been investigated for future large fusion experimental devices. A thermal spraying method is employed to coat the insulation or conduction materials on the structural components. Al 2 O 3 has been selected as an insulation material, while Cr 3 C 2 -NiCr and WC-NiCr have been chosen as conduction materials. These materials were coated on stainless steel base plates to examine the basic characteristics of the coated layers, such as their adhesive strength to the base plate and electrical resistance. It was found that they have sufficient electrical insulation and conduction properties, respectively. In addition, the sliding tests of the coated layers showed sufficient frictional properties. The applicability of the spraying method was examined on a 100mm x 1000mm surface and found to be applicable for large surfaces in fusion experimental devices. (orig.)

Some implications for mirror research of the coupling between fusion economics and fusion physics

International Nuclear Information System (INIS)

Post, R.F.

1980-01-01

The thesis is made that physics understanding and innovation represent two of the most important ingredients of any program to develop fusion power. In this context the coupling between these and the econmics of yet-to-be realized fusion power plants is explored. The coupling is two-way: realistic evaluations of the economic (and environmental) requirements for fusion power systems can influence the physics objectives of present-day fusion research programs; physics understanding and innovative ideas can favorably impact the future economics of fusion power systems. Of equal importance is the role that physics/innovation can have on the time scale for the first practical demonstration of fusion power. Given the growing worldwide need for long-term solutions to the problem of energy it is claimed to be crucial that fusion research be carried out on a broad base and in a spirit that both facilitates the growth of physics understanding and fosters innovation. Developing this theme, some examples of mirror-based fusion system concepts are given that illustrate the coupling here described

Nuclear Fusion with Polarized Nucleons & PolFusion

CERN Document Server

Engels, Ralf; Büscher, Markus; Vasilyev, Alexander

2016-01-01

This book offers a detailed examination of the latest work on the potential of polarized fuel to realize the vision of energy production by nuclear fusion. It brings together contributions from nuclear physicists and fusion physicists with the aims of fostering exchange of information between the two communities, describing the current status in the field, and examining new ideas and projects under development. It is evident that polarized fuel can offer huge improvements for the first generation of fusion reactors and open new technological possibilities for future generations, including neutron lean reactors, which could be the most popular and sustainable energy production option to avoid environmental problems. Nevertheless, many questions must be resolved before polarized fuel can be used for energy production in the different reactor types. Readers will find this book to be a stimulating source of information on the key issues. It is based on contributions from leading scientists delivered at the meetin...

Management of Waste from the Fusion Experimental Breeder

Institute of Scientific and Technical Information of China (English)

1998-01-01

<正> Fusion breeder might be an essential intermediate application of fusion energy at earlier term, which has the potential to provide plenty of commercial fissile fuel. Based on fusion physics and technologies available at present and in near future, the realistic Fusion Experimental Breeder, FEB-E was designed. The obiectives of the FEB-E are to demonstrate the engineering feasibility of

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.

Nuclear data requirements for fusion reactor nucleonics

International Nuclear Information System (INIS)

Bhat, M.R.; Abdou, M.A.

1980-01-01

Nuclear data requirements for fusion reactor nucleonics are reviewed and the present status of data are assessed. The discussion is divided into broad categories dealing with data for Fusion Materials Irradiation Test Facility (FMIT), D-T Fusion Reactors, Alternate Fuel Cycles and the Evaluated Data Files that are available or would be available in the near future

Recent developments concerning the fusion; Developpements recents sur la fusion

Energy Technology Data Exchange (ETDEWEB)

Jacquinot, J. [CEA/Cadarache, Dept. de Recherches sur la Fusion Controlee, DRFC, 13 - Saint Paul lez Durance (France); Andre, M. [CEA/DAM Ile de France, 91 - Bruyeres Le Chatel (France); Aymar, R. [ITER Joint Central Team Garching, Muenchen (Germany)] [and others

2000-09-04

Organized the 9 march 2000 by the SFEN, this meeting on the european program concerning the fusion, showed the utility of the exploitation and the enhancement of the actual technology (JET, Tore Supra, ASDEX) and the importance of the Europe engagement in the ITER program. The physical stakes for the magnetic fusion have been developed with a presentation of the progresses in the knowledge of the stability limits. A paper on the inertial fusion was based on the LMJ (Laser MegaJoule) project. The two blanket concepts chosen in the scope of the european program on the tritium blankets, have been discussed. These concepts will be validated by irradiation tests in the ITER-FEAT and adapted for a future reactor. (A.L.B.)

Intitutional constraints to fusion commercialization

International Nuclear Information System (INIS)

1979-10-01

The major thrust of this report is that the long time frame associated with the development of commercial fusion systems in the context of the commercialization and institutional history of an allied technology, fission-power, suggests that fusion commercialization will not occur without active and broad-based support on the part of the Nation's political leaders. Its key recommendation is that DOE fusion planners devote considerable resources to analytical efforts aimed at determining the need for fusion and the timing of that need, in order to convince policymakers that they need do more than preserve fusion as an option for application at some indefinite point in the future. It is the thesis of the report that, in fact, an act of political vision on the part of the Nation's leaders will be required to accomplish fusion commercialization

Generic magnetic fusion reactor cost assessment

International Nuclear Information System (INIS)

Sheffield, J.

1985-01-01

The Fusion Energy Division of the Oak Ridge National Laboratory discusses ''generic'' magnetic fusion reactors. The author comments on DT burning magnetic fusion reactor models being possibly operational in the 21st century. Representative parameters from D-T reactor studies are given, as well as a shematic diagram of a generic fusion reactor. Values are given for winding pack current density for existing and future superconducting coils. Topics included are the variation of the cost of electricity (COE), the dependence of the COE on the net electric power of the reactor, and COE formula definitions

Economics of fusion research

Energy Technology Data Exchange (ETDEWEB)

None, None

1977-10-15

This report provides the results of a study of methods of economic analysis applied to the evaluation of fusion research. The study recognizes that a hierarchy of economic analyses of research programs exists: standard benefit-cost analysis, expected value of R and D information, and expected utility analysis. It is shown that standard benefit-cost analysis, as commonly applied to research programs, is inadequate for the evaluation of a high technology research effort such as fusion research. A methodology for performing an expected value analysis is developed and demonstrated and an overview of an approach to perform an expected utility analysis of fusion research is presented. In addition, a potential benefit of fusion research, not previously identified, is discussed and rough estimates of its magnitude are presented. This benefit deals with the effect of a fusion research program on optimal fossil fuel consumption patterns. The results of this study indicate that it is both appropriate and possible to perform an expected value analysis of fusion research in order to assess the economics of a fusion research program. The results indicate further that the major area of benefits of fusion research is likely due to the impact of a fusion research program on optimal fossil fuel consumption patterns and it is recommended that this benefit be included in future assessments of fusion research economics.

Economics of fusion research

International Nuclear Information System (INIS)

1977-01-01

This report provides the results of a study of methods of economic analysis applied to the evaluation of fusion research. The study recognizes that a hierarchy of economic analyses of research programs exists: standard benefit-cost analysis, expected value of R and D information, and expected utility analysis. It is shown that standard benefit-cost analysis, as commonly applied to research programs, is inadequate for the evaluation of a high technology research effort such as fusion research. A methodology for performing an expected value analysis is developed and demonstrated and an overview of an approach to perform an expected utility analysis of fusion research is presented. In addition, a potential benefit of fusion research, not previously identified, is discussed and rough estimates of its magnitude are presented. This benefit deals with the effect of a fusion research program on optimal fossil fuel consumption patterns. The results of this study indicate that it is both appropriate and possible to perform an expected value analysis of fusion research in order to assess the economics of a fusion research program. The results indicate further that the major area of benefits of fusion research is likely due to the impact of a fusion research program on optimal fossil fuel consumption patterns and it is recommended that this benefit be included in future assessments of fusion research economics

Directions for improved fusion reactors

International Nuclear Information System (INIS)

Krakowski, R.A.; Miller, R.L.; Delene, J.G.

1986-01-01

Conceptual fusion reactor studies over the past 10 to 15 years have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points towards smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. A generic fusion physics/engineering/costing model is used to provide a quantiative basis for these arguments for specific fusion concepts

Results of nuclear fusion development

International Nuclear Information System (INIS)

Yamamoto, Kenzo

1975-01-01

Compared with the nuclear fission research which followed that in advanced countries, Japan has treaded on its own track in nuclear fusion development; in the former, she had been far behind other leading countries. Characteristic of the efforts in Japan is the collaboration with educational institutions. Works are now carried out mainly in Tokamak plasma confinement, though other means being studied simultaneously. The nation's fusion research program is the realization of a fusion reactor at the turn of the present century, based on the world-level results attained with Tokamak. Past developments in the nuclear fusion research, the current status, and aspects for the future are discribed. (Mori, K.)

Multilayer mirror based monitors for impurity controls in large fusion reactor type devices

International Nuclear Information System (INIS)

Regan, S.P.; May, M.J.; Soukhanovskii, V.; Finkenthal, M.; Moos, H.W.

1995-01-01

Multilayer Mirror (MLM) based monitors are compact, high throughput diagnostics capable of extracting XUV emissions (the wavelength range including the soft-x-ray and the extreme ultraviolet, 10 angstrom to 304 angstrom) of impurities from the harsh environment of large fusion reactor type devices. For several years the Plasma Spectroscopy Group at Johns Hopkins University has investigated the application of MLM based XUV spectroscopic diagnostics for magnetically confined fusion plasmas. MLM based monitors have been constructed for and extensively used on DIII-D, Alcator C-mod, TEXT, Phaedrus-T, and CDX-U tokamaks to study the impurity behavior of elements ranging from He to Mo. On ITER MLM based devices would be used to monitor the spectral line emissions from Li I-like to F I-like charge states of Fe, Cr, and Ni, as well as extractors for the bands of emissions from high Z elements such as Mo or W for impurity controls of the fusion plasma. In addition to monitoring the impurity emissions from the main plasma, MLM based devices can also be adapted for radiation measurements of low Z elements in the divertor. The concepts and designs of these MLM based monitors for impurity controls in ITER will be presented. The results of neutron irradiation experiments of the MLMs performed in the Los Alamos Spallation Radiation Effects Facility (LASREF) at the Los Alamos National Laboratory will also be discussed. These preliminary neutron exposure studies show that the dispersive and reflective qualities of the MLMs were not affected in a significant manner

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)

Fusion Technologies: 2nd Karlsruhe International Summer School

International Nuclear Information System (INIS)

Bahm, W.

2008-01-01

Nuclear fusion promises to deliver a future non-polluting energy supply with nearly unlimited fuel reserves. To win young scientists and engineers for nuclear fusion, the Karlsruhe Research Center, together with other partners in the European Fusion Education Network being established by the European Commission, organizes the 2nd Karlsruhe International Summer School on Fusion Technologies on September 1-12, 2008. The program covers all key technologies necessary for construction and operation of a fusion reactor. (orig.)

Accelerators for heavy ion fusion

International Nuclear Information System (INIS)

Bangerter, R.O.

1985-10-01

Large fusion devices will almost certainly produce net energy. However, a successful commercial fusion energy system must also satisfy important engineering and economic constraints. Inertial confinement fusion power plants driven by multi-stage, heavy-ion accelerators appear capable of meeting these constraints. The reasons behind this promising outlook for heavy-ion fusion are given in this report. This report is based on the transcript of a talk presented at the Symposium on Lasers and Particle Beams for Fusion and Strategic Defense at the University of Rochester on April 17-19, 1985

Applications of Skyrme energy-density functional to fusion reactions spanning the fusion barriers

International Nuclear Information System (INIS)

Liu Min; Wang, Ning; Li Zhuxia; Wu Xizhen; Zhao Enguang

2006-01-01

The Skyrme energy density functional has been applied to the study of heavy-ion fusion reactions. The barriers for fusion reactions are calculated by the Skyrme energy density functional with proton and neutron density distributions determined by using restricted density variational (RDV) method within the same energy density functional together with semi-classical approach known as the extended semi-classical Thomas-Fermi method. Based on the fusion barrier obtained, we propose a parametrization of the empirical barrier distribution to take into account the multi-dimensional character of real barrier and then apply it to calculate the fusion excitation functions in terms of barrier penetration concept. A large number of measured fusion excitation functions spanning the fusion barriers can be reproduced well. The competition between suppression and enhancement effects on sub-barrier fusion caused by neutron-shell-closure and excess neutron effects is studied

The JET project and the European fusion research programme

International Nuclear Information System (INIS)

Wuester, H.-O.

1984-01-01

The paper concerns the Joint European Torus (JET) project and the European Fusion Research Programme. Fusion as an energy source and commercial fusion power are briefly discussed. The main features of the JET apparatus and the tokamak magnetic field configuration are given. Also described are the specific aims of JET, and the proposed future fusion reactor programme. (U.K.)

Fusion energy

International Nuclear Information System (INIS)

Anon.

1979-01-01

The efforts of the Chemical Technology Division in fusion energy include the areas of fuel handling, processing, and containment. Current studies are concerned largely with the development of vacuum pumps for fusion reactors and experiments and with development and evaluation of techniques for recovering tritium from solid or liquid breeding blankets. In addition, a small effort is devoted to support of the ORNL design of a major Tokamak experiment, The Next Step (TNS)

Large aperture components for solid state laser fusion systems

International Nuclear Information System (INIS)

Simmons, W.W.

1978-01-01

Solid state lasers for fusion experiments must reliably deliver maximum power to small (approximately .5 mm) targets from stand-off focal distances of 1 m or more. This requirement places stringent limits upon the optical quality, resistance to damage, and overall performance of the several major components--amplifiers, Faraday isolators, spatial filters--in each amplifier train. Component development centers about achieving (1) highest functional material figure of merit, (2) best optical quality, and (3) maximum resistance to optical damage. Specific examples of the performance of large aperture components will be presented within the context of the Argus and Shiva laser systems, which are presently operational at Lawrence Livermore Laboratory. Shiva comprises twenty amplifiers, each of 20 cm output clear aperture. Terawatt beams from these amplifiers are focused through two opposed, nested clusters of f/6 lenses onto such targets. Design requirements upon the larger aperture Nova laser components, up to 35 cm in clear aperture, will also be discussed; these pose a significant challenge to the optical industry

Atomic physics issues in fusion

International Nuclear Information System (INIS)

Post, D.E.

1982-01-01

Atomic physics issues have played a large role in controlled fusion research. A general introduction to the present role of atomic processes in both inertial and magnetic controlled fusion work is presented. (Auth.)

Economic analysis of fusion breeders

International Nuclear Information System (INIS)

Delene, J.G.

1985-01-01

This paper presents a study of the economic performance of Fission/Fusion Hybrid devices. This work takes fusion breeder cost estimates and applies methodology and cost factors used in the fission reactor programs to compare fusion breeders with Liquid Metal Fast Breeder Reactors (LMFBR). The results of the analysis indicate that the Hybrid will be in the same competitive range as proposed LMFBRs and have the potential to provide economically competitive power in a future of rising uranium prices. The sensitivity of the results to variations in key parameters is included

Present status and future prospects for direct drive laser fusion

International Nuclear Information System (INIS)

Bodner, S.E.

1986-01-01

If one assumes that the best short wavelength laser will have an efficiency of 5--7%, and if one assumes that reasonable cost electricity requires that the product of laser efficiency and pellet gain be greater than 10--15, then pellet grains for laser fusion must be at least 150--300. The only laser fusion concept with any potential for energy applications then seems to be directly driven targets with moderately thin shells and 1/4 micron KrF laser light. This direct drive concept has potential pellet energy gains of 200--300

Fusion technology programme

International Nuclear Information System (INIS)

Finken, D.

1984-04-01

KfK participates to the Fusion Technology Programme of the European Community. Most of the work in progress addresses the Next European Torus (NET) and the long term technology aspects as defined in the 82/86 programme. A minor part serves to preparation of future contributions and to design studies on fusion concepts in a wider perspective. The Fusion Technology Programme of Euratom covers mainly aspects of nuclear engineering. Plasma engineering, heating, refueling and vacuum technology are at present part of the Physics Programme. In view of NET, integration of the different areas of work will be mandatory. KfK is therefore prepared to address technical aspects beyond the actual scope of the physics experiments. The technology tasks are reported project wise under title and code of the Euratom programme. Most of the projects described here are shared with other European fusion laboratories as indicated in the table annexed to this report. (orig./GG)

Fusion power plant economics

International Nuclear Information System (INIS)

Miller, R.L.

1996-01-01

The rationale, methodology, and updated comparative results of cost projections for magnetic-fusion-energy central-station electric power plants are considered. Changing market and regulatory conditions, particularly in the U.S., prompt fundamental reconsideration of what constitutes a competitive future energy-source technology and has implications for the direction and emphasis of appropriate near-term research and development programs, for fusion and other advanced generation systems. 36 refs., 2 figs., 2 tabs

Report on research and development work 1985 on the nuclear fusion project. Annual report of the Association KfK-Euratom

International Nuclear Information System (INIS)

Finken, D.

1986-05-01

The Nuclear Research Centre Karlsruhe and the Max Planck Institute for Plasma Physics together form the Nuclear Fusion Development Association. The partners collaborate with the aim of creating the physical and technical preconditions for the use of the energy released by nuclear fusion and to plan and carry out future large-scale experiments. The work of the Nuclear Research Centre Karlsruhe on fusion with magnetic containment is included in the nuclear fusion project and is part of the European fusion technology programme. The work is supported by an association contract between KfK and Euratom by the European Commission. Connections are built up between areas of work and new projects are prepared by supplementary KfK contributions, mostly studies. This is done with regard to the expansion of the technology programme to be expected for future years and the planning activities for NET. The reports collected here are contributions of the KfK institutes in 1985. The appendix contains a list of the tasks which KfK has taken over from the fusion technology programme of the EEC. References to the institutes' contributions make the assignment of textual contributions easier. (orig.) [de

Fusion power plant availability study

International Nuclear Information System (INIS)

Ladra, D.; Sanguinetti, G.P.; Stube, E.

2001-01-01

The consideration of fusion as an alternative energy source will need to demonstrate that Fusion Power Plant (FPP) design, operating and maintenance characteristics meet the electrical market requirements forecast for the second half of this century. Until now, fusion has been developed in the framework of research and development programmes following natural technological trends. To bring a greater sense of realism to commercial viability and to guarantee that technology-driven fusion development responds to the demands of the market, a conceptual study of future commercial FPPs has been performed with a Power Plant Availability (PPA) study aimed at identifying the aspects affecting the availability and generating costs of FPPs. EFET, who has also been involved in the study, can visualise it from two different points of view; that of the industry (ANSALDO, IBERTEF, SIEMENS, NNC) and that of the utilities (BELGATOM, FRAMATOME, FORTUM). The work carried out covered the following points: socio-economic forecasting; safety and licensing; operation and maintenance; waste and decommissioning; availability and reliability. The following are the most relevant findings, conclusions and recommendations for all these aspects: Demonstrate definitively that the physical principles of nuclear fusion have been validated by means of experiments; Establish a European Industrial Group to support the demonstration phases; Create the financial and contracting framework required to construct these installations. Secure the necessary budgets for the European Union's 5th and 6th Research Programmes. Look for supplementary long term financing sources; The existing Regulatory Bodies should combine to form a single Working Group with responsibility for fusion reactor safety and licensing activities, working on the harmonisation of the regulatory processes, developing FPP safety criteria and guidelines and reviewing industry standards; To be competitive, FPPs should have high availability

Alternative fusion concepts

International Nuclear Information System (INIS)

Rostagni, G.

1981-01-01

The paper reports the discussions and statements made by the participants on the actual state and future of five different approaches on the fusion concept; they are the following: bumpy torus, reversed-field pinch, open-ended configurations, compact toroids and stellarators. Tables show for each concept parameters that represent the achieved results; data expected for future devices and extrapolations on reactor requirements are included

Radiation facilities for fusion-reactor first-wall and blanket structural-materials development

International Nuclear Information System (INIS)

Klueh, R.L.; Bloom, E.E.

1981-12-01

Present and future irradiation facilities for the study of fusion reactor irradiation damage are reviewed. Present studies are centered on irradiation in accelerator-based neutron sources, fast- and mixed-spectrum fission reactors, and ion accelerators. The accelerator-based neutron sources are used to demonstrate damage equivalence between high-energy neutrons and fission reactor neutrons. Once equivalence is demonstrated, the large volume of test space available in fission reactors can be used to study displacement damage, and in some instances, the effects of high-helium concentrations and the interaction of displacement damage and helium on properties. Ion bombardment can be used to study the mechanisms of damage evolution and the interaction of displacement damage and helium. These techniques are reviewed, and typical results obtained from such studies are examined. Finally, future techniques and facilities for developing damage levels that more closely approach those expected in an operating fusion reactor are discussed

Fusion reactor radioactive waste management

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-01-01

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

Development of fusion fuel cycles: Large deviations from US defense program systems

Energy Technology Data Exchange (ETDEWEB)

Klein, James Edward, E-mail: james.klein@srnl.doe.gov; Poore, Anita Sue; Babineau, David W.

2015-10-15

Highlights: • All tritium fuel cycles start with a “Tritium Process.” All have similar tritium processing steps. • Fusion tritium fuel cycles minimize process tritium inventories for various reasons. • US defense program facility designs did not minimize in-process inventories. • Reduced inventory tritium facilities will lower public risk. - Abstract: Fusion energy research is dominated by plasma physics and materials technology development needs with smaller levels of effort and funding dedicated to tritium fuel cycle development. The fuel cycle is necessary to supply and recycle tritium at the required throughput rate; additionally, tritium confinement throughout the facility is needed to meet regulatory and environmental release limits. Small fuel cycle development efforts are sometimes rationalized by stating that tritium processing technology has already been developed by nuclear weapons programs and these existing processes only need rescaling or engineering design to meet the needs of fusion fuel cycles. This paper compares and contrasts features of tritium fusion fuel cycles to United States Cold War era defense program tritium systems. It is concluded that further tritium fuel cycle development activities are needed to provide technology development beneficial to both fusion and defense programs tritium systems.

ANNETTE Project: Contributing to The Nuclearization of Fusion

Science.gov (United States)

Ambrosini, W.; Cizelj, L.; Dieguez Porras, P.; Jaspers, R.; Noterdaeme, J.; Scheffer, M.; Schoenfelder, C.

2018-01-01

The ANNETTE Project (Advanced Networking for Nuclear Education and Training and Transfer of Expertise) is well underway, and one of its work packages addresses the design, development and implementation of nuclear fusion training. A systematic approach is used that leads to the development of new training courses, based on identified nuclear competences needs of the work force of (future) fusion reactors and on the current availability of suitable training courses. From interaction with stakeholders involved in the ITER design and construction or the JET D-T campaign, it became clear that the lack of nuclear safety culture awareness already has an impact on current projects. Through the collaboration between the European education networks in fission (ENEN) and fusion (FuseNet) in the ANNETTE project, this project is well positioned to support the development of nuclear competences for ongoing and future fusion projects. Thereby it will make a clear contribution to the realization of fusion energy.

ANNETTE Project: Contributing to The Nuclearization of Fusion

Directory of Open Access Journals (Sweden)

Ambrosini W.

2018-01-01

Full Text Available The ANNETTE Project (Advanced Networking for Nuclear Education and Training and Transfer of Expertise is well underway, and one of its work packages addresses the design, development and implementation of nuclear fusion training. A systematic approach is used that leads to the development of new training courses, based on identified nuclear competences needs of the work force of (future fusion reactors and on the current availability of suitable training courses. From interaction with stakeholders involved in the ITER design and construction or the JET D-T campaign, it became clear that the lack of nuclear safety culture awareness already has an impact on current projects. Through the collaboration between the European education networks in fission (ENEN and fusion (FuseNet in the ANNETTE project, this project is well positioned to support the development of nuclear competences for ongoing and future fusion projects. Thereby it will make a clear contribution to the realization of fusion energy.

Fusion technology programme

International Nuclear Information System (INIS)

Finken, D.

1986-05-01

In 1982, KfK joined the fusion programme of EURATOM as a further association introducing its experience in nuclear technology. KfK closely cooperates with IPP Garching, the two institutions forming a research unit aiming at planning and realization of future development steps of fusion. KfK has combined its forces in the Nuclear Fusion Project (PKF) with participation of several KfK departments to the project tasks. Previous work of KfK in magnetic fusion has addressed mainly superconducting magnets, plasma heating by cluster ions and studies on structural materials. At present, emphasis of our work has concentrated increasingly on the nuclear part, i.e. the first wall and blanket structures and the elements of the tritium extraction and purification system. Associated to this component development are studies of remote maintenance and safety. Most of the actual work addresses NET, the next step to a demonstration of fusion feasibility. NET is supposed to follow JET, the operating plasma physics experiment of Euratom, on the 1990's. Detailed progress of the work in the past half year is described in this report. (orig./GG)

Controlled thermonuclear fusion: research on magnetic fusion

International Nuclear Information System (INIS)

Paris, P.J.

1988-12-01

Recent progress in thermonuclear fusion research indicates that the scientists' schedule for the demonstration of the scientific feasibility will be kept and that break-even will be attained in the course of the next decade. To see the implementation of ignition, however, the generation of future experiments must be awaited. These projects are currently under study. With technological research going on in parallel, they should at the same time contribute to the design of a reactor. Fusion reactors will be quite different from the fission nuclear reactors we know, and the waste of the plants will also be of a different nature. It is still too early to define the precise design of a fusion reactor. On the basis of a toric machine concept like that of the tokamak, we can, however, envisage that the problems with which we are confronted will be solved one after the other. As we have just seen, these will be the objectives of the future experimental installations where ignition will be possible and where the flux of fast neutrons will be so strong that they will allow the study of low-activation materials which will be used in the structure of the reactor. But this is also a task in which from now onwards numerous laboratories in Europe and in the world participate. The works are in fact punctiform, and often the mutual incidences can only be determined by an approach simulated by numerical codes. (author) 19 figs., 6 tabs., 8 refs

Heavy-ion accelerator research for inertial fusion

International Nuclear Information System (INIS)

1987-08-01

Thermonuclear fusion offers a most attractive long-term solution to the problem of future energy supplies: The fuel is virtually inexhaustible and the fusion reaction is notably free of long-lived radioactive by-products. Also, because the fuel is in the form of a plasma, there is no solid fuel core that could melt down. The DOE supports two major fusion research programs to exploit these virtues, one based on magnetic confinement and a second on inertial confinement. One part of the program aimed at inertial fusion is known as Heavy Ion Fusion Accelerator Research, or HIFAR. In this booklet, the aim is to place this effort in the context of fusion research generally, to review the brief history of heavy-ion fusion, and to describe the current status of the HIFAR program

Quasi-elastic scattering an alternative tool for mapping the fusion barriers for heavy-ion induced fusion reaction

International Nuclear Information System (INIS)

Behera, B.R.

2016-01-01

Heavy element synthesis through heavy-ion induced fusion reaction is an active field in contemporary nuclear physics. Exact knowledge of fusion barrier is one of the essential parameters for planning any experiments for heavy element production. Theoretically there are many models available to predict the exact barrier. Though these models are successful for predicting the fusion of medium mass nuclei, it somehow fails for predicting the exact location of barrier for fusion of heavy nuclei. Experimental determination of barrier for such reactions is required for future experiments for the synthesis of heavy elements. Traditionally fusion barrier is determined taking a double derivative of fusion excitation function. However, such method is difficult in case of fusion of heavy nuclei due to its very low fusion/capture cross section and its experimental complications. Alternatively fusion barrier can be determined by measuring the quasi-elastic cross section at backward angles. This method can be applied for determining the fusion barrier for the fusion of heavy nuclei. Experimental determination of fusion barrier by different methods and comparison of the fusion excitation function and quasi-elastic scattering methods for the determination of fusion barrier are reviewed. At IUAC, New Delhi recently a program has been started for the measurement of fusion barrier through quasi-elastic scattering methods. The experimental facility and the first results of the experiments carried out with this facility are presented. (author)

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

The near future of nuclear fusion

International Nuclear Information System (INIS)

Grenier, E.

2000-01-01

In this short article the author tries to find an explanation about the withdraw of the Usa from the ITER project. According to the author the American economy is not so flourishing as it seems, it is only the IT (information technologies) sector that is attracting huge foreign investments. Moreover state agencies such as Nasa have difficulties to recruit talented people because they are lured by easy money earned in the new economy. The whole of the ITER project has been reduced: the volume of plasma will be 840 m 3 (instead of 2000 m 3 ) for a fusion power of 500 MW (instead of 1500 MW). Canada is standing for hosting the building site. (A.C.)

Glucocorticoid induced osteopenia in cancellous bone of sheep: validation of large animal model for spine fusion and biomaterial research

DEFF Research Database (Denmark)

Ding, Ming; Cheng, Liming; Bollen, Peter

2010-01-01

STUDY DESIGN: Glucocorticoid with low calcium and phosphorus intake induces osteopenia in cancellous bone of sheep. OBJECTIVE: To validate a large animal model for spine fusion and biomaterial research. SUMMARY OF BACKGROUND DATA: A variety of ovariectomized animals has been used to study...... osteoporosis. Most experimental spine fusions were based on normal animals, and there is a great need for suitable large animal models with adequate bone size that closely resemble osteoporosis in humans. METHODS: Eighteen female skeletal mature sheep were randomly allocated into 3 groups, 6 each. Group 1 (GC......-1) received prednisolone (GC) treatment (0.60 mg/kg/day, 5 times weekly) for 7 months. Group 2 (GC-2) received the same treatment as GC-1 for 7 months followed by 3 months without treatment. Group 3 was left untreated and served as the controls. All sheep received restricted diet with low calcium...

Utilization of fusion neutrons in the tokamak fusion test reactor for blanket performance testing and other nuclear engineering experiments

International Nuclear Information System (INIS)

Caldwell, C.S.; Pettus, W.G.; Schmotzer, J.K.; Welfare, F.; Womack, R.

1979-01-01

In addition to developing a set of reacting-plasma/blanket-neutronics benchmark data, the TFTR fusion application experiments would provide operational experience with fast-neutron dosimetry and the remote handling of blanket modules in a tokamak reactor environment; neutron streaming and hot-spot information invaluable for the optimal design of penetrations in future fusion reactors; and the identification of the most damage-resistant insulators for a variety of fusion-reactor components

Progress in fusion technology in the U.S. magnetic fusion program

International Nuclear Information System (INIS)

Dowling, R.J.; Beard, D.S.; Haas, G.M.; Stone, P.M.; George, T.V.

1987-01-01

In this paper the authors discuss the major technological achievements that have taken place during the past few years in the U.S. magnetic fusion program which have contributed to the global efforts. The goal has been to establish the scientific and technological base required for fusion energy. To reach this goal the fusion RandD program is focused on four key technical issues: determine the optimum configuration of magnetic confinement systems; determine the properties of burning plasmas; develop materials for fusion systems; and establish the nuclear technology of fusion systems. The objective of the fusion technology efforts has been to develop advanced technologies and provide the necessary support for research of these four issues. This support is provided in a variety of areas such as: high vacuum technology, large magnetic field generation by superconducting and copper coils, high voltage and high current power supplies, electromagnetic wave and particle beam heating systems, plasma fueling, tritium breeding and handling, remote maintenance, energy recovery. The U.S. Fusion Technology Program provides major support or has the primary responsibility in each of the four key technical issues of fusion, as described in the Magnetic Fusion Program Plan of February 1985. This paper has summarized the Technology Program in terms of its activities and progress since the Proceedings of the SOFT Conference in 1984

Ceramics for fusion devices

International Nuclear Information System (INIS)

Clinard, F.W. Jr.

1984-01-01

Ceramics are required for a number of applications in fusion devices, among the most critical of which are magnetic coil insulators, windows for RF heating systems, and structural uses. Radiation effects dominate consideration of candidate materials, although good pre-irradiation properties are a requisite. Materials and components can be optimized by careful control of chemical and microstructural content, and application of brittle material design and testing techniques. Future directions for research and development should include further extension of the data base in the areas of electrical, structural, and thermal properties; establishment of a fission neutron/fusion neutron correlation including transmutation gas effects; and development of new materials tailored to meet the specific needs of fusion reactors

Hydrogen production in early generation fusion power plant and its socio-economic implication

International Nuclear Information System (INIS)

Konishi, S.; Yamamoto, Y.

2007-01-01

Full text: This paper describes technical possibility of high temperature blanket for the early generation of fusion power plant and its application to hydrogen production. Its anticipated implication and strategy from the socio-economic aspects will be also discussed. Material and energy balances, such as fuel supply and delivery of product energy from fusion plants, as well as waste discharge and accident scenario that lead to environmental impact, are characterized by blanket concepts. Thus blankets are considered to dominate the feature of fusion energy that should respond to the requirements of the sponsors, i.e., public and future market. Fusion blanket concept based on the combinations of LiPb and SiC materials are regarded as a candidate for ITER/TBM, and at the same time, applied in various DEMO designs encompassing high temperature output. Recent developments of SiC-LiPb blanket in Japan, EU, US or China suggests staged development paths starting from TBMs and targeting high temperature blanket and efficient energy output from early generation plants. These strategies are strongly affected by the views of these parties on fusion energy, from the aspects of socio-economics. Hydrogen production process with the high temperature blanket is one of the most important issues, because temperature range much higher than is possible with current or near future fission plants are needed, suggesting market possibility different from that of fission. Fuel cycles, particularly lithium supply and TBR control will be also important. Self-sustained fusion fuel cycle requires technical capability to maintain the lithium contents. Liquid blanket has an advantage in continuous and real-time control TBR in a plant, but large amount of lithium-6 and initial tritium supply remains as issues. As for the environmental effect, normal operation release, assumed accidental scenario, and rad-waste will be the key issue to dominate social acceptance of fusion. (author)

Hydrogen production in early generation fusion power plant and its socio-economic implication

International Nuclear Information System (INIS)

Konishi, Satoshi; Yamamoto, Yasushi

2008-01-01

This paper describes technical possibility of high temperature blanket for the early generation of fusion power plant and its application to hydrogen production. Its anticipated implication and strategy from the socio-economic aspects will be also discussed. Material and energy balances, such as fuel supply and delivery of product energy from fusion plants, as well as waste discharge and accident scenario that lead to environmental impact, are characterized by blanket concepts. Thus blankets are considered to dominate the feature of fusion energy that should respond to the requirements of the sponsors, i.e., public and future market. Fusion blanket concept based on the combinations of LiPb and SiC materials are regarded as a candidate for ITER/TBM, and at the same time, applied in various DEMO designs encompassing high temperature output. Recent developments of SiC-LiPb blanket in Japan, EU, US or China suggests staged development paths starting from TBMs and targeting high temperature blanket and efficient energy output from early generation plants. These strategies are strongly affected by the views of these parties on fusion energy, from the aspects of socio-economics. Hydrogen production process with the high temperature blanket is one of the most important issues, because temperature range much higher than is possible with current or near future fission plants are needed, suggesting market possibility different from that of fission. Fuel cycles, particularly lithium supply and TBR control will be also important. Self-sustained fusion fuel cycle requires technical capability to maintain the lithium contents. Liquid blanket has an advantage in continuous and real-time control TBR in a plant, but large amount of lithium-6 and initial tritium supply remains as issues. As for the environmental effect, normal operation release, assumed accidental scenario, and rad-waste will be the key issue to dominate social acceptance of fusion. (author)

Fusion for Energy: The European joint undertaking for ITER and the development of fusion energy

International Nuclear Information System (INIS)

Diegele, E.

2009-01-01

environment and conditions. Materials and materials technologies (fabrication, welding, joining) have to be fully qualified in front of a rigorous licensing process within the next decade. Therefore, materials development for DEMO is based on present technologies and knowledge with some reasonable extrapolation. The 9% Cr steel EUROFER steel is the primary EU candidate structural material. For increased thermal efficiency the temperature window of the structural materials needs to be enlarged. Various ODS (Oxide Dispersion Strengthened) Fe-Cr-steels are candidates for higher temperature application. The large fraction of high energy neutrons in the fusion neutron spectrum results in gaseous transmutations (He and H) that are more than one order of magnitude higher than in fission. Even though fission based material test reactors are the essential and indispensable pillar of the current and future irradiation qualification programme, they can not provide sufficient data for a successful licensing process towards DEMO. For this reason, the construction and use of a facility called IFMIF, designed for simulating as closely a possible the fusion neutron spectrum, is mandatory. Meantime, and complimentary, an enhanced material science programme should increase knowledge and understanding of radiation effects. The focus of this programme for the next decade should be on the development and validation of predictive capabilities for modelling micro-structural evolution and mechanical properties of EUROFER-type steels under fusion reactor relevant conditions, addressing in particular the Helium issue. In a longer term perspective, this should result in the implementation of an integrated approach involving modelling and model-oriented experimental validation into a strategy of accelerated development and testing of candidate fusion materials, material systems and material technologies. (author)

Fusion an introduction to the physics and technology of magnetic confinement fusion

CERN Document Server

Stacey, Weston M

2010-01-01

This second edition of a popular textbook is thoroughly revised with around 25% new and updated content.It provides an introduction to both plasma physics and fusion technology at a level that can be understood by advanced undergraduates and graduate students in the physical sciences and related engineering disciplines.As such, the contents cover various plasma confinement concepts, the support technologies needed to confine the plasma, and the designs of ITER as well as future fusion reactors.With end of chapter problems for use in courses.

Strong neutron sources - How to cope with weapon material production capabilities of fusion and spallation neutron sources?

International Nuclear Information System (INIS)

Englert, M.; Franceschini, G.; Liebert, W.

2013-01-01

In this article we investigate the potential and relevance for weapon material production in future fusion power plants and spallation neutron sources (SNS) and sketch what should be done to strengthen these technologies against a non-peaceful use. It is shown that future commercial fusion reactors may have military implications: first, they provide an easy source of tritium for weapons, an element that does not fall under safeguards and for which diversion from a plant could probably not be detected even if some tritium accountancy is implemented. Secondly, large fusion reactors - even if not designed for fissile material breeding - could easily produce several hundred kg Pu per year with high weapon quality and very low source material requirements. If fusion-only reactors will prevail over fission-fusion hybrids in the commercialization phase of fusion technology, the safeguard challenge will be more of a legal than of a technical nature. In pure fusion reactors (and in most SNS) there should be no nuclear material present at any time by design. The presence of undeclared nuclear material would indicate a military use of the plant. This fact offers a clear-cut detection criterion for a covert use of a declared facility. Another important point is that tritium does not fall under the definition of 'nuclear material', so a pure fusion reactor or a SNS that do not use nuclear materials are not directly falling under any international non-proliferation treaty requirements. Non-proliferation treaties have to be amended to take into account that fact. (A.C.)

Synthetic fuels and fusion

Energy Technology Data Exchange (ETDEWEB)

Fillo, J A; Powell, J; Steinberg, M [Brookhaven National Lab., Upton, NY (USA)

1981-03-01

The decreasing availability of fossil fuels emphasizes the need to develop systems which will produce synthetic fuel to substitute for and supplement the natural supply. An important first step in the synthesis of liquid and gaseous fuels is the production of hydrogen. Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. equal to 40-60% and hydrogen production efficiencies by high temperature electrolysis of approx. equal to 50-70% are projected for fusion reactors using high temperature blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long-term, there could be a gradual transition to an inexhaustible energy system based solely on fusion.

Laser fusion and future energy sources - some recent results

International Nuclear Information System (INIS)

Hora, H.

1979-01-01

While the laser fusion is at present producing more genuine fusion neutrons than the tokamak with magnetic confinement, if use of short laser pulses is preferred, the then appearing nonlinear effect causes considerable complications. Nonlinear processes for the preferred geometry of perpendicular incidence can avoid the problems of resonance absorption, while parametric instabilities have no quantitative influence on the energy balance. The early stages of interaction show the generation of thick 'cold' compressing plasma blocks which can be used for a nonlinear force fast pusher compression of high efficiency (low entropy production). A short time interaction results in a fast thermalization of the plasma corona by soliton decay and this provides the necessary condition for Nuckolls' gasdynamic ablation compression. For longer duration of high intensity irradiation, a pulsation of reflectivity and thermalization will complicate the interaction

Protein-induced fusion can be modulated by target membrane lipids through a structural switch at the level of the fusion peptide

NARCIS (Netherlands)

Pecheur, EI; Martin, [No Value; Bienvenue, A; Ruysschaert, JM; Hoekstra, D

2000-01-01

Regulatory features of protein-induced membrane fusion are largely unclear, particularly at the level of the fusion peptide. Fusion peptides being part of larger protein complexes, such investigations are met with technical limitations. Here, we show that the fusion activity of influenza virus or

Manufacturing W fibre-reinforced Cu composite pipes for application as heat sink in divertor targets of future nuclear fusion reactors

Energy Technology Data Exchange (ETDEWEB)

Mueller, Alexander v.; You, Jeong-Ha [Max-Planck-Institut fuer Plasmaphysik, 85748 Garching (Germany); Ewert, Dagmar [Institut fuer Textil- und Verfahrenstechnik Denkendorf, 73770 Denkendorf (Germany); Siefken, Udo [Louis Renner GmbH, 85221 Dachau (Germany)

2016-07-01

An important plasma-facing component (PFC) in future nuclear fusion reactors is the so-called divertor which allows power exhaust and removal of impurities from the main plasma. The most highly loaded parts of a divertor are the target plates which have to withstand intense particle bombardment. This intense particle bombardment leads to high heat fluxes onto the target plates which in turn lead to severe thermomechanical loads. With regard to future nuclear fusion reactors, an improvement of the performance of divertor targets is desirable in order to ensure reliable long term operation of such PFCs. The performance of a divertor target is most closely linked to the properties of the materials that are used for its design. W fibre-reinforced Cu (Wf/Cu) composites are regarded as promising heat sink materials in this respect. These materials do not only feature adequate thermophysical and mechanical properties, they do also offer metallurgical flexibility as their microstructure and hence their macroscopic properties can be tailored. The contribution will point out how Wf/Cu composites can be used to realise an advanced design of a divertor target and how these materials can be fabricated by means of liquid Cu infiltration.

Controlled nuclear fusion apparatus

International Nuclear Information System (INIS)

Bussard, R.W.; Coppi, B.

1982-01-01

A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and/or recycled for subsequent use within the same blanket region. Thermonuclear ignition of the plasma is obtained by feeding neutral fusible gas into the plasma in a controlled manner such that charged particle heating produced by the fusion reaction is utilized to bootstrap the device to a region of high temperatures and high densities wherein charged particle heating is sufficient to overcome radiation and thermal conductivity losses. The high density plasma produces a large radiation and particle flux on the first wall of the plasma core region thereby necessitating replacement of the core from the blanket region from time to time. A series of potentially disposable and replaceable central core regions are disclosed for a large-scale economical electrical power generating plant

Mirror fusion reactors

International Nuclear Information System (INIS)

Carlson, G.A.; Moir, R.W.

1978-01-01

We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

Mirror fusion reactors

International Nuclear Information System (INIS)

Anon.

1978-01-01

Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

Analysis of an induction linac driver system for inertial fusion

International Nuclear Information System (INIS)

Hovingh, J.; Brady, V.O.; Faltens, A.; Keefe, D.; Lee, E.P.

1987-07-01

A linear induction accelerator that produces a beam of energetic (5 to 20 GeV) heavy (130 to 210 amu) ions is a prime candidate as a driver for inertial fusion. Continuing developments in sources for ions with charge state greater than unity allow a potentially large reduction in the driver cost and an increase in the driver efficiency. The use of high undepressed tunes (σ 0 ≅ 85 0 ) and low depressed tunes (σ ≅ 8.5 0 ) also contributes to a potentially large reduction in the driver cost. The efficiency and cost of the induction linac system are discussed as a function of output energy and pulse repetition frequency for several ion masses and charge states. The cost optimization code LIACEP, including accelerating module alternatives, transport modules, and scaling laws, is presented. Items with large cost-leverage are identified as a guide to future research activities and development of technology that can yield substantial reductions in the accelerator system cost and improvement in the accelerator system efficiency. Finally, a cost-effective strategy using heavy ion induction linacs in a development scenario for inertial fusion is presented. 34 refs., 6 figs., 7 tabs

Nuclear Propulsion through Direct Conversion of Fusion Energy: The Fusion Driven Rocket

Science.gov (United States)

Slough, John; Pancotti, Anthony; Kirtley, David; Pihl, Christopher; Pfaff, Michael

2012-01-01

The future of manned space exploration and development of space depends critically on the creation of a dramatically more proficient propulsion architecture for in-space transportation. A very persuasive reason for investigating the applicability of nuclear power in rockets is the vast energy density gain of nuclear fuel when compared to chemical combustion energy. Current nuclear fusion efforts have focused on the generation of electric grid power and are wholly inappropriate for space transportation as the application of a reactor based fusion-electric system creates a colossal mass and heat rejection problem for space application.

An Indispensable Truth How Fusion Power Can Save the Planet

CERN Document Server

Chen, Francis F

2011-01-01

Both global warming and oil shortage can be solved by controlled fusion, a clean power source that will serve mankind for millennia.� The idea of hydrogen fusion as well as its difficulties are presented in non-technical language to dispel the notion that fusion is always 50 years away.� This book also summarizes the evidence for climate change and explains the principles of both fossil and "green" energy sources to show that fusion is the best alternative for central-station power in the near term as well as the far future. Praise for An Indispensable Truth: How Fusion Power Can Save the Planet: "In this study Professor Chen outlines the underlying physics, recent progress in achieving advanced plasmas and magnetic confinement, and hopes for the future. He recognizes the difficulties that remain in engineering a fusion reactor, but he remains optimistic regarding ultimate success, yet fearful of the consequences were we to fail."- James R. Schlesinger, former Chairman, Atomic Energy Commission; Director,...

Initial experiments with the FOM-Fusion-FEM

International Nuclear Information System (INIS)

Verhoeven, A.G.A.; Bongers, W.A.; Caplan, M.; Dijk, G. van; Elzendoorn, B.S.Q.

1995-01-01

A Free Electron Maser is being built for ECRH applications on future fusion research devices such as ITER. A unique feature of the Dutch FOM-Fusion-FEM is the possibility to tune the frequency over the entire range from 130 to 260 GHz while the output power exceeds 1 MW

Fusion power in the E.E.C. - some considerations concerning the future programme

International Nuclear Information System (INIS)

Carruthers, R.

1976-01-01

The problems of fusion reactor technology, the assessment of potential reactor systems and an estimate of the overall investment of manpower likely to be needed to reach a practical fusion power reactor are presented. (U.K.)

Application of high temperature superconductors for fusion

International Nuclear Information System (INIS)

Fietz, W.H.; Heller, R.; Schlachter, S.I.; Goldacker, W.

2011-01-01

The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70 kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2 kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads - 20 kA and 6 leads - 25.7 kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads. With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65 K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20 kA at high fields well above 10 T. The high field rules BiSCCO superconductors out at temperatures above 50 K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for

T2*-weighted image/T2-weighted image fusion in postimplant dosimetry of prostate brachytherapy

International Nuclear Information System (INIS)

Katayama, Norihisa; Takemoto, Mitsuhiro; Yoshio, Kotaro

2011-01-01

Computed tomography (CT)/magnetic resonance imaging (MRI) fusion is considered to be the best method for postimplant dosimetry of permanent prostate brachytherapy; however, it is inconvenient and costly. In T2 * -weighted image (T2 * -WI), seeds can be easily detected without the use of an intravenous contrast material. We present a novel method for postimplant dosimetry using T2 * -WI/T2-weighted image (T2-WI) fusion. We compared the outcomes of T2 * -WI/T2-WI fusion-based and CT/T2-WI fusion-based postimplant dosimetry. Between April 2008 and July 2009, 50 consecutive prostate cancer patients underwent brachytherapy. All the patients were treated with 144 Gy of brachytherapy alone. Dose-volume histogram (DVH) parameters (prostate D90, prostate V100, prostate V150, urethral D10, and rectal D2cc) were prospectively compared between T2 * -WI/T2-WI fusion-based and CT/T2-WI fusion-based dosimetry. All the DVH parameters estimated by T2 * -WI/T2-WI fusion-based dosimetry strongly correlated to those estimated by CT/T2-WI fusion-based dosimetry (0.77≤ R ≤0.91). No significant difference was observed in these parameters between the two methods, except for prostate V150 (p=0.04). These results show that T2 * -WI/T2-WI fusion-based dosimetry is comparable or superior to MRI-based dosimetry as previously reported, because no intravenous contrast material is required. For some patients, rather large differences were observed in the value between the 2 methods. We thought these large differences were a result of seed miscounts in T2 * -WI and shifts in fusion. Improving the image quality of T2 * -WI and the image acquisition speed of T2 * -WI and T2-WI may decrease seed miscounts and fusion shifts. Therefore, in the future, T2 * -WI/T2-WI fusion may be more useful for postimplant dosimetry of prostate brachytherapy. (author)

Economic goals and requirements for competitive fusion energy

International Nuclear Information System (INIS)

Miller, R.L.

1998-01-01

Future economic competitiveness, coupled to and constrained by environmental and safety characteristics, continues to provide a central strategic motivation and concern for fusion research. Attention must also be paid to the evolving cost projections of future fusion competitors, with appropriate consideration of externalized impacts, insofar as they establish the eventual market-penetration context and also influence the near-term funding climate for fusion R and D. With concept optimization and selection in mind, tradeoffs among system power density, recirculating power, plant availability (reflecting both forced and planned outages), complexity, and structural materials and coolant choices are best monitored and resolved in the context of their impacts on capital and operating costs, which, together with low fuel costs and financial assumptions, determine the projected life-cycle product cost of fusion. Considerations deriving from deregulation and privatization are elucidated, as are possible implications of modern investment-analysis methods. (orig.)

Gene Fusion Markup Language: a prototype for exchanging gene fusion data.

Science.gov (United States)

Kalyana-Sundaram, Shanker; Shanmugam, Achiraman; Chinnaiyan, Arul M

2012-10-16

An avalanche of next generation sequencing (NGS) studies has generated an unprecedented amount of genomic structural variation data. These studies have also identified many novel gene fusion candidates with more detailed resolution than previously achieved. However, in the excitement and necessity of publishing the observations from this recently developed cutting-edge technology, no community standardization approach has arisen to organize and represent the data with the essential attributes in an interchangeable manner. As transcriptome studies have been widely used for gene fusion discoveries, the current non-standard mode of data representation could potentially impede data accessibility, critical analyses, and further discoveries in the near future. Here we propose a prototype, Gene Fusion Markup Language (GFML) as an initiative to provide a standard format for organizing and representing the significant features of gene fusion data. GFML will offer the advantage of representing the data in a machine-readable format to enable data exchange, automated analysis interpretation, and independent verification. As this database-independent exchange initiative evolves it will further facilitate the formation of related databases, repositories, and analysis tools. The GFML prototype is made available at http://code.google.com/p/gfml-prototype/. The Gene Fusion Markup Language (GFML) presented here could facilitate the development of a standard format for organizing, integrating and representing the significant features of gene fusion data in an inter-operable and query-able fashion that will enable biologically intuitive access to gene fusion findings and expedite functional characterization. A similar model is envisaged for other NGS data analyses.

Methods of economic analysis applied to fusion research. Fifth annual report

International Nuclear Information System (INIS)

1981-01-01

In this and previous efforts, ECON has provided economic assessment of a fusion research program. This phase of study has focused on the future markets for fusion energy and the economics of fusion in those markets. These tasks were performed: (1) fusion market growth, (2) inflation vs. capital investment decisions, and (3) economics of cogeneration

Charging large capacitor banks for fusion research using HVDC conversion equipment

International Nuclear Information System (INIS)

Brown, D.R.; Bird, W.L.; Huang, Y.C.; Tolk, K.

1984-01-01

Fundamental considerations in the choice of a continuous duty capacitor bank charging system using HVDC conversion equipment are presented. Large systems of the type used in fusion related research pose significant system related problems if they are to be supplied from a conventional power grid. Schemes for conditioning the required power in order to overcome such problems are presented and evaluated. A resonant charging system is examined in detail and shown to be superior in a number of ways to constant current charging. Results of digital computer simulation studies are used to demonstrate the feasibility of the system. It is shown that the resonant charging system reduces rectifier capacity, simplifies control and reduces reactive power fluctuations. Sequential bank charging and use of a motor-generator set are presented as techniques for compensation of real power fluctuations and a comparison on the basis of initial cost is presented

Cell fusion and nuclear fusion in plants.

Science.gov (United States)

Maruyama, Daisuke; Ohtsu, Mina; Higashiyama, Tetsuya

2016-12-01

Eukaryotic cells are surrounded by a plasma membrane and have a large nucleus containing the genomic DNA, which is enclosed by a nuclear envelope consisting of the outer and inner nuclear membranes. Although these membranes maintain the identity of cells, they sometimes fuse to each other, such as to produce a zygote during sexual reproduction or to give rise to other characteristically polyploid tissues. Recent studies have demonstrated that the mechanisms of plasma membrane or nuclear membrane fusion in plants are shared to some extent with those of yeasts and animals, despite the unique features of plant cells including thick cell walls and intercellular connections. Here, we summarize the key factors in the fusion of these membranes during plant reproduction, and also focus on "non-gametic cell fusion," which was thought to be rare in plant tissue, in which each cell is separated by a cell wall. Copyright © 2016 Elsevier Ltd. All rights reserved.

High-energy fusion: A quest for a simple, small and environmentally acceptable colliding-beam fusion power source

International Nuclear Information System (INIS)

Maglich, B.

1978-01-01

Fusion goals should be lowered for a speedier research and development of a less ambitious but a workable 'low-gain fusion power amplifier', based on proven technologies and concepts. The aim of the Migma Program of Controlled Fusion is a small (10-15 liters) fusion power source based on colliding beams instead of plasma or laser heating. Its scientific and technological 'philosophy' is radically different from that of the governmental fusion programs of the USA and USSR. Migmacell uses radiation-free fuels, ('advanced fuels'), rather than tritium. Economic projections show that such a smaller power cell can be econonomically competitive in spite of its low power gain, because it can be mass produced. Power stations could be made either large or small and the power transmission and distribution pattern in the nation would change. An interspersion of energy resources would result. Minifusion opens the possibility to smaller countries (and medium size institutions of large countries), for participation in fusion research; this resource of research talent is presently excluded from fusion by the high cost of the mainline governmental research (over $ 200 million for one experimental fusion device, as compared to $ 1 million for migmacell). The time-scale for obtaining experimental results is reduced from decades to years. Experimental accomplishments to date and the further research needed, are presented. (orig.) [de

Materials technology for fusion - Current status and future requirements

International Nuclear Information System (INIS)

Gold, R.E.; Bloom, E.E.; Clinard, F.W. Jr.; Smith, D.L.; Stevenson, R.D.; Wolfer, W.G.

1981-01-01

The general status of the materials research and development activities currently under way in support of controlled thermonuclear fusion reactors in the United States is reviewed. In the area of magnetic confinement configurations, attention is given to development programs for first wall materials, which are at various stages for possible austenitic stainless steels, high-strength Fe-Ni-Cr alloys, reactive and refractory metal alloys, specially designed long-range ordered and rapidly solidified alloys, and ferritic/martensitic steels, and for tritium breeding materials, electrical insulators, ceramics, and coolants. The development of materials for inertial confinement reactors is also surveyed in relation to the protection scheme employed for the first wall and the effects of pulsed neutron irradiation. Finally, the materials requirements and selection procedures for the ETF/INTOR and Starfire tokamak reactor designs are examined. Needs for the expansion of research on nonfirst-wall materials and inertial confinement fusion reactor material requirements are pointed out

Neutral beam systems for the magnetic fusion program

International Nuclear Information System (INIS)

Beal, J.W.; Staten, H.S.

1977-01-01

The attainment of economic, safe fusion power has been described as the most sophisticated scientific problem ever attacked by mankind. The presently established goal of the magnetic fusion program is to develop and demonstrate pure fusion central electric power stations for commercial applications. Neutral beam heating systems are a basic component of the tokamak and mirror experimental fusion plasma confinement devices. The requirements placed upon neutral beam heating systems are reviewed. The neutral beam systems in use or being developed are presented. Finally, the needs of the future are discussed

Efforts in Public Relations on Fusion in Europe

Science.gov (United States)

Ongena, J.; van Oost, G.

2001-10-01

An overview will be given of different published materials currently in use in Europe for public relations on fusion. We will also present a CD-ROM for individual and classroom use, containing (i) a general background on different energy forms, (ii) general principles of fusion, (iii) current research efforts and (iv) future prospects of fusion. This CD-ROM is currently in English, German, French, Spanish, Portuguese and Italian. Fusion posters developed in collaboration with CPEP in Dutch, French, German, Italian, Spanish and Portuguese will be shown. Several new brochures and leaflets intended to increase the public awareness on fusion in Europe will be on display.

Starpower: the US and the international quest for fusion energy

International Nuclear Information System (INIS)

1987-10-01

This report, requested by the House Committee on Science, Space, and Technology and endorsed by the Senate Committee on Energy and Natural Resources, reviews the status of magnetic-confinement fusion research and compares its progress with the requirements for development of a useful energy technology. The report does not analyze inertial-confinement fusion research, which is overseen by the House and Senate Armed Services Committees. Contents include: Executive Summary; Introduction and overview; History of fusion research; Fusion science and technology; Fusion as an energy program; Fusion as a research program; Fusion as an international program; Future paths for the magnetic-fusion program; Appendixes--(Non-electric applications for fusion, Other approaches to fusion, Data for figures, List of acronyms and glossary)

Fusion hindrance in reactions with very heavy ions: Border between normal and hindered fusion

International Nuclear Information System (INIS)

Shen Caiwan; Li Qingfeng; Boilley, David; Shen Junjie; Abe, Yasuhisa

2011-01-01

The fusion hindrance in heavy-ion collisions is studied in the framework of the two-center liquid drop model. It appears that the neck and the radial degrees of freedom might both be hampered by an inner potential barrier on their path between the contact configuration to the compound nucleus. Heavy-ion reactions with and without the two kinds of fusion hindrance are classified through systematic calculations. It is found that the number of reactions without radial fusion hindrance is much smaller than that without neck fusion hindrance, and for both kinds of fusion hindrance the number of reactions without fusion hindrance at small mass-asymmetry parameter α is smaller than that at large α. In the formation of a given compound nucleus, if a reaction with α c is not hindered, then other reactions with α>α c are also not hindered, as is well known experimentally.

Research on the wetted first wall concept for future laser fusion reactors. Final report No. 1, October 1, 1974--January 31, 1976

International Nuclear Information System (INIS)

Hoffman, M.A.; Munir, Z.A.

1976-01-01

Research is in progress to determine the feasibility of the wetted first wall concept for a future laser fusion reactor. The basic idea involves the use of a thin coating of lithium on the inner wall of the laser fusion containment vessel to protect it from the micro-explosion blast debris. This report contains a review of the available information on contact angles and wettability of alkali metals on various metal substrates as well as a review of literature on thin falling liquid films. A proposed experiment to measure the contact angles of lithium on stainless steel and niobium is described. The requirements for a second experiment to measure certain key characteristics of thin falling films are also included

Fusion power in the E.E.C

International Nuclear Information System (INIS)

Carruthers, R.

1976-01-01

The work outlines firstly the aims of a fusion reactor development programme, as well as the role regarding plasma physics in this and then deals with the present situation of system studies on a series of various types of fusion apparatus. 15 test systems are listed and discussed. After working out the differences between the terms 'fusion technology' and 'fusion reactor technology', factors based on the organization of technology research and development, and the future technology research and development of the E.E.C. are dealt with. Problems concerning time-tables, resources, and the priorities to be set are touched upon. Suggestions are made regarding the carring-out of a European fusion reactor development programme. Problems concerning fusion reactor technology and some dealing with the tokamak and reversed field pinch are listed and discussed in two appendixes. (GG) [de

Assessment of the Fusion Energy Sciences Program. Final Report

International Nuclear Information System (INIS)

2001-01-01

An assessment of the Office of Fusion Energy Sciences (OFES) program with guidance for future program strategy. The overall objective of this study is to prepare an independent assessment of the scientific quality of the Office of Fusion Energy Sciences program at the Department of Energy. The Fusion Science Assessment Committee (FuSAC) has been appointed to conduct this study

Development and evaluation of plasma facing materials for future thermonuclear fusion reactors

International Nuclear Information System (INIS)

Linke, J.; Pintsuk, G.; Roedig, M.; Schmidt, A.; Thomser, C.

2010-01-01

More and more attention is directed towards thermonuclear fusion as a possible future energy source. Major advantages of this energy conversion technology are the almost inexhaustible resources and the option to produce energy without CO 2 -emissions. However, in the most advanced field of magnetic plasma confinement a number of technological challenges have to be met. In particular high-temperature resistant and plasma compatible meterials have to be developed and qualified which are able to withstand the extreme environments in a commercial thermonuclear power reactor. The plasma facing materials (PEMs) and components (PFCs) in such fusion devices, i.e. the first wall (FW), the limiters and the divertor, are strongly affected by the plasma wall interaction processes and the applied intense thermal loads during plasma operation. On the one hand, these mechanisms have a strong influence on the plasma performance; on the other hand, they have major impact on the lifetime of the plasma facing armour. Materials for plasma facing components have to fulfill a number of requirements. First of all the materials have to be plasma compatible, i.e. they should exhibit a low atomic number to avoid radiative losses whenever atoms from the wall material will be ionized in the plasma. In addition, the materials must have a high melting point, a high thermal conductivity, and adequate mechanical properties. To select the most suitable material candidates, a comprehensive data base is required which includes all thermo-physical and mechanical properties. In present-day and next step devices the resulting thermal steady state heat loads to the first wall remain below 1 MWm -2 , meanwhile the limiters and the divertor are expected to be exposed to power densities being at least one order of magnitude above the FW-level, i.e. up to 20 MWm -2 for next step tokamaks such as ITER or DEMO. These requirements are responsible for high demands on the selection of qualified PFMs and heat

Development and evaluation of plasma facing materials for future thermonuclear fusion reactors

Energy Technology Data Exchange (ETDEWEB)

Linke, J.; Pintsuk, G.; Roedig, M.; Schmidt, A.; Thomser, C. [Forschungszentrum Juelich GmbH, EURATOM Association, Juelich (Germany)

2010-07-01

More and more attention is directed towards thermonuclear fusion as a possible future energy source. Major advantages of this energy conversion technology are the almost inexhaustible resources and the option to produce energy without CO{sub 2}-emissions. However, in the most advanced field of magnetic plasma confinement a number of technological challenges have to be met. In particular high-temperature resistant and plasma compatible meterials have to be developed and qualified which are able to withstand the extreme environments in a commercial thermonuclear power reactor. The plasma facing materials (PEMs) and components (PFCs) in such fusion devices, i.e. the first wall (FW), the limiters and the divertor, are strongly affected by the plasma wall interaction processes and the applied intense thermal loads during plasma operation. On the one hand, these mechanisms have a strong influence on the plasma performance; on the other hand, they have major impact on the lifetime of the plasma facing armour. Materials for plasma facing components have to fulfill a number of requirements. First of all the materials have to be plasma compatible, i.e. they should exhibit a low atomic number to avoid radiative losses whenever atoms from the wall material will be ionized in the plasma. In addition, the materials must have a high melting point, a high thermal conductivity, and adequate mechanical properties. To select the most suitable material candidates, a comprehensive data base is required which includes all thermo-physical and mechanical properties. In present-day and next step devices the resulting thermal steady state heat loads to the first wall remain below 1 MWm{sup -2}, meanwhile the limiters and the divertor are expected to be exposed to power densities being at least one order of magnitude above the FW-level, i.e. up to 20 MWm{sup -2} for next step tokamaks such as ITER or DEMO. These requirements are responsible for high demands on the selection of qualified PFMs

On impact fusion

International Nuclear Information System (INIS)

Winterberg, F.

1997-01-01

Impact fusion is a promising, but much less developed road towards inertial confinement fusion. It offers an excellent solution to the so-called stand-off problem for thermonuclear microexplosions but is confronted with the challenge to accelerate macroscopic particles to the needed high velocities of 10 2 -10 3 km/s. To reach these velocities, two ways have been studied in the past. The electric acceleration of a beam of microparticles, with the particles as small as large clusters, and the magnetic acceleration of gram-size ferromagnetic or superconducting projectiles. For the generation of an intense burst of soft X-rays used for the indirect drive, impact fusion may offer new promising possibilities

Inherent/passive safety in fusion power plants

International Nuclear Information System (INIS)

Piet, S.J.; Crocker, J.G.

1986-01-01

The concept of inherent or passive safety for fusion energy is explored, defined, and partially quantified. Four levels of safety assurance are defined, which range from true inherent safety to passive safety to protection via active engineered safeguard systems. Fusion has the clear potential for achieving inherent or passive safety, which should be an objective of fusion research and design. Proper material choice might lead to both inherent/passive safety and high mass power density, improving both safety and economics. When inherent or passive safety is accomplished, fusion will be well on the way to achieving its ultimate potential and to be a truly superior energy source for the future

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.

Irradiation-induced fusion between giant vesicles and photoresponsive large unilamellar vesicles containing malachite green derivative.

Science.gov (United States)

Uda, Ryoko M; Yoshikawa, Yuki; Kitaba, Moe; Nishimoto, Noriko

2018-07-01

Light-initiated fusion between vesicles has attracted much attention in the research community. In particular, fusion between photoresponsive and non-photoresponsive vesicles has been of much interest in the development of systems for the delivery of therapeutic agents to cells. We have performed fusion between giant vesicles (GVs) and photoresponsive smaller vesicles containing malachite green (MG) derivative, which undergoes ionization to afford a positive charge on the molecule by irradiation. The fusion proceeds as the concentration of GV lipid increases toward equimolarity with the lipid of the smaller vesicle. It is also dependent on the molar percentage of photoionized MG in the lipid of the smaller vesicle. On the other hand, the fusion is hardly affected by the anionic component of the GV. The photoinduced fusion was characterized by two methods, involving the mixing of lipid membranes and of aqueous contents. Fluorescence microscopy revealed that irradiation triggered the fusion of a single GV with the smaller vesicles containing MG. Copyright © 2018 Elsevier B.V. All rights reserved.

Fusion methodologies in crisis management higher level fusion and decision making

CERN Document Server

Scott, Peter

2016-01-01

This book emphasizes a contemporary view on the role of higher level fusion in designing crisis management systems. It provides the formal foundations, architecture, and implementation strategies required for building dynamic current and future situational pictures. It goes on to discuss the state-of-the-art computational approaches to designing such processes and their inherent challenges. This book integrates recent advances in decision theory with those in fusion methodology to define an end-to-end framework for decision support in crisis management. The text discusses modern fusion and decision support methods for dealing with heterogeneous and often unreliable, low fidelity, contradictory, and redundant data and information, as well as rare, unknown, unconventional or even unimaginable critical situations. The book also examines the role of context in situation management, cognitive aspects of decision making and situation management, approaches to domain representation, visualization, as well as the rol...

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

Fusion Programme SCK-CEN - Annual Report 2010

Energy Technology Data Exchange (ETDEWEB)

Massaut, V.

2010-10-15

In 2010 SCK-CEN centred his activities in fusion Research and Development around four main poles: 1) the studies of the first wall of future DEMO facility and plasma wall interactions, using the recently refurbished plasmatron VISIONI; 2) the study of the radiation resistance of optical and specific diagnostic components and the development and prototyping of a Fiber Optics Current Sensor (FOCS) for measuring Tokamak plasma current for long plasma pulses and without embarked electronics: 3) the further study, by irradiation and mechanical testing but also by modelling, of the future structural material for a fusion plant, the RAFM Eurofer and the development and characterization of ODS-Eurofer; 4) specific fusion socio-economic studies on fusion, based on the specific developments carried out for fusion and radioactive waste management. SCK-CEN is also strongly involved in the Broader Approach agreement as Designated Institution for the Belgian State, having a coordinating and managing role for all Belgian activities in this agreement. The present report is structured following the work programme 2010 of the Association. Some former activities form the old-EFDA have been grouped with new ones in coherent and collaborative packages. Most activities of SCK-CEN are, and have always been, carried out under EFDA task agreements.

Fusion Programme SCK-CEN - Annual Report 2010

International Nuclear Information System (INIS)

Massaut, V.

2010-01-01

In 2010 SCK-CEN centred his activities in fusion Research and Development around four main poles: 1) the studies of the first wall of future DEMO facility and plasma wall interactions, using the recently refurbished plasmatron VISIONI; 2) the study of the radiation resistance of optical and specific diagnostic components and the development and prototyping of a Fiber Optics Current Sensor (FOCS) for measuring Tokamak plasma current for long plasma pulses and without embarked electronics: 3) the further study, by irradiation and mechanical testing but also by modelling, of the future structural material for a fusion plant, the RAFM Eurofer and the development and characterization of ODS-Eurofer; 4) specific fusion socio-economic studies on fusion, based on the specific developments carried out for fusion and radioactive waste management. SCK-CEN is also strongly involved in the Broader Approach agreement as Designated Institution for the Belgian State, having a coordinating and managing role for all Belgian activities in this agreement. The present report is structured following the work programme 2010 of the Association. Some former activities form the old-EFDA have been grouped with new ones in coherent and collaborative packages. Most activities of SCK-CEN are, and have always been, carried out under EFDA task agreements.

The present role of superconductivity in fusion

International Nuclear Information System (INIS)

Shimamoto, S.

1986-01-01

After completion of large fusion devices in the world, such as JT-60, JET and TFTR, high temperature plasma is proceeding to critical condition for fusion. The devices up to now use mainly conventional magnet. However, for the next generation machine which demonstrates fusion reaction, deuterium-tritium burning, superconducting magnet system is indispensable from view point of both net energy extraction and capacity limitation of power supply. In order to realize such a large and complicated system, a lot of development works is being carried out. This paper describes required parameters of superconducting magnet and helium refrigerator, the state of plasma condition and superconducting magnet. It is shown that the present technology of superconducting magnet is not so far from realization of fusion experimental reactor

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)

Failure rate data for fusion safety and risk assessment

International Nuclear Information System (INIS)

Cadwallader, L.C.

1993-01-01

The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components

[Research progress of multi-model medical image fusion and recognition].

Science.gov (United States)

Zhou, Tao; Lu, Huiling; Chen, Zhiqiang; Ma, Jingxian

2013-10-01

Medical image fusion and recognition has a wide range of applications, such as focal location, cancer staging and treatment effect assessment. Multi-model medical image fusion and recognition are analyzed and summarized in this paper. Firstly, the question of multi-model medical image fusion and recognition is discussed, and its advantage and key steps are discussed. Secondly, three fusion strategies are reviewed from the point of algorithm, and four fusion recognition structures are discussed. Thirdly, difficulties, challenges and possible future research direction are discussed.

Public Relations on Fusion in Europe

Science.gov (United States)

Ongena, J.; van Oost, G.; Paris, P. J.

2000-10-01

A summary will be presented of PR efforts on fusion energy research in Europe. A 3-D movie of a fusion research experimental reactor has been realized at the start of this year. It has been made entirely on virtual animation basis. Two versions exists, a short version of 3 min., as a video clip, and a longer version of nearly 8 min. Both could be viewed in 3D, using special projections and passive glasses or in normal VHS video projections. A new CD-ROM for individual and classroom use will be presented, discussing (i) the different energy forms, (ii) general principles of fusion, (iii) current research efforts and (iv) future prospects of fusion. This CD-ROM is now produced in English, German, French, Spanish, Italian and Portuguese Several new brochures and leaflets intended to increase the public awareness on fusion in Europe will be on display.

Breeder control fusion reactor. Topical interview

Energy Technology Data Exchange (ETDEWEB)

Schlueter, A [Max-Planck-Institut fuer Plasmaphysik, Garching/Muenchen (Germany, F.R.)

1977-09-01

The energy sources of the future are extremely controversial. The consumption of fossil fuel shall decrease during the next decades, because exhaustion of the resources, pollution, increase of CO/sub 2/ in the atmosphere and other reasons. But at present the question it not yet settled which alternative energy system should replace the fossil fuel. First of all nuclear energy in the form of fission reactions seems to come into operation to a larger extent. The next step may be the controlled thermonuclear fusion reaction. Furthermore, a comparison between fusion and fission is given which shows that fusion would bring about less risks than the breeders. An advantage of the fusion reactor would be the fact that the fuel cycle is closed. Unfortunately, the physical questions are not as yet satisfactorily clarified so that one cannot be sure whether a fusion reactor can really be built.

1986 progress report on R and D work of the Nuclear Fusion Project (PKF)

International Nuclear Information System (INIS)

Kast, G.

1987-03-01

The Kernforschungszentrum Karlsruhe (KfK) and the Max-Planck-Institute for Plasma Physics, Garching, have joined to form the Entwicklungsgemeinschaft Kernfusion, and under this roof perform research work on the physical and technical conditions and requirements of using the energy from nuclear fusion, and to plan the design and the construction of the necessary equipment for future large-scale experiments. The activities of the KfK for the development of fusion devices with magnetic confinement have been concentrated in the Nuclear Fusion Project, which cooperates in the European Fusion Technology Programme, on the basis of an association agreement between KfK and Euratom, supported by the European Commission. Supplementary KfK contributions, studies in most cases, create a connection between various fields of work, and prepare the road for new tasks, which in the years to come will be found in the extension of the Fusion Technology Programme and the planning work for NET. The reports collected in this annual survey are contributions from KfK Institutes of the year 1986. An annex presents the Easks taken over by KfK within the Fusion Technology Programme of the EC, and notes on the KfK Institutes taking part in the particular activities facilitate reference to the individual, full-text reports. (orig.) [de

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.

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.

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

Nuclear fusion

International Nuclear Information System (INIS)

Huber, H.

1978-01-01

A comprehensive survey is presented of the present state of knowledge in nuclear fusion research. In the first part, potential thermonuclear reactions, basic energy balances of the plasma (Lawson criterion), and the main criteria to be observed in the selection of appropriate thermonuclear reactions are dealt with. This is followed by a discussion of the problems encountered in plasma physics (plasma confinement and heating, transport processes, plasma impurities, plasma instabilities and plasma diagnostics) and by a consideration of the materials problems involved, such as material of the first wall, fuel inlet and outlet, magnetic field generation, as well as repair work and in-service inspections. Two main methods have been developed to tackle these problems: reactor concepts using the magnetic pinch (stellarator, Tokamak, High-Beta reactors, mirror machines) on the one hand, and the other concept using the inertial confinement (laser fusion reactor). These two approaches and their specific problems as well as past, present and future fusion experiments are treated in detail. The last part of the work is devoted to safety and environmental aspects of the potential thermonuclear aspects of the potential thermonuclear reactor, discussing such problems as fusion-specific hazards, normal operation and potential hazards, reactor incidents, environmental pollution by thermal effluents, radiological pollution, radioactive wastes and their disposal, and siting problems. (orig./GG) [de

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.

Status report on controlled nuclear fusion as a source of hydrogen energy

International Nuclear Information System (INIS)

Powell, J.

1975-01-01

The present status of controlled fusion research is reviewed. Possible future reseach is also described. Tokamak systems using both fusion and fissionable fuels are discussed. Various aspects of hydrogen production by fusion reactors are described according to cost and economics. auth)

The use of industrial type control and monitoring components for a large fusion experiment

International Nuclear Information System (INIS)

Hemming, O.N.; Manduchi, G.; Luchetta, A.; Schmidt, V.; Vitturi, S.

1994-01-01

RFX is one of the large nuclear fusion experiments within the framework of the co-ordinated nuclear fusion research programme of the European Community. During the control system design phase in 1986, the increase in power and flexibility of industrial type programmable controllers lead to the decision for a complete physical split of control, monitoring and data acquisition functions according to speed requirements, allowing the exploitation of the relative advantages of both CAMAC and programmable controllers. The 'slow' control and monitoring functions (for about 4000 digital and 200 analog I/O signals with scanning times of similar 1 second) have been implemented using a series of networked industrial PLCs and personal computers. This has allowed us to choose from a wide range of off-the-shelf hardware and software components for the plant interface and to utilize specialized expertise from the industrial field for the application software implementation. The paper gives the expectations and results gained from this design choice and how it has influenced the decisions for the evolution of the system over the next few years with the utilization of new industrial hardware components. Details are also given regarding the system integration (via the Ethernet network) with the VAX-based CAMAC frontend fast control and data-acquisition system. ((orig.))

Accelerated plan to develop magnetic fusion energy

International Nuclear Information System (INIS)

Fowler, T.K.

1986-01-01

We have shown that, despite funding delays since the passage of the Magnetic Fusion Engineering Act of 1980, fusion development could still be carried to the point of a demonstration plant by the year 2000 as called for in the Act if funding, now about $365 million per year, were increased to the $1 billion range over the next few years (see Table I). We have also suggested that there may be an economic incentive for the private sector to become in accelerating fusion development on account of the greater stability of energy production costs from fusion. Namely, whereas fossil fuel prices will surely escalate in the course of time, fusion fuel will always be abundantly available at low cost; and fusion technology poses less future risk to the public and the investor compared to conventional nuclear power. In short, once a fusion plant is built, the cost of generating electricity mainly the amortization of the plant capital cost - would be relatively fixed for the life of the plant. In Sec. V, we found that the projected capital cost of fusion plants ($2000 to $4000 per KW/sub e/) would probably be acceptable if fusion plants were available today

Magnetic-fusion energy and computers

International Nuclear Information System (INIS)

Killeen, J.

1982-01-01

The application of computers to magnetic fusion energy research is essential. In the last several years the use of computers in the numerical modeling of fusion systems has increased substantially. There are several categories of computer models used to study the physics of magnetically confined plasmas. A comparable number of types of models for engineering studies are also in use. To meet the needs of the fusion program, the National Magnetic Fusion Energy Computer Center has been established at the Lawrence Livermore National Laboratory. A large central computing facility is linked to smaller computer centers at each of the major MFE laboratories by a communication network. In addition to providing cost effective computing services, the NMFECC environment stimulates collaboration and the sharing of computer codes among the various fusion research groups

Inertial-confinement fusion with lasers

International Nuclear Information System (INIS)

Betti, R.; Hurricane, O. A.

2016-01-01

The quest for controlled fusion energy has been ongoing for over a half century. The demonstration of ignition and energy gain from thermonuclear fuels in the laboratory has been a major goal of fusion research for decades. Thermonuclear ignition is widely considered a milestone in the development of fusion energy, as well as a major scientific achievement with important applications to national security and basic sciences. The U.S. is arguably the world leader in the inertial con fment approach to fusion and has invested in large facilities to pursue it with the objective of establishing the science related to the safety and reliability of the stockpile of nuclear weapons. Even though significant progress has been made in recent years, major challenges still remain in the quest for thermonuclear ignition via laser fusion

Magnetic fusion energy and computers

International Nuclear Information System (INIS)

Killeen, J.

1982-01-01

The application of computers to magnetic fusion energy research is essential. In the last several years the use of computers in the numerical modeling of fusion systems has increased substantially. There are several categories of computer models used to study the physics of magnetically confined plasmas. A comparable number of types of models for engineering studies are also in use. To meet the needs of the fusion program, the National Magnetic Fusion Energy Computer Center has been established at the Lawrence Livermore National Laboratory. A large central computing facility is linked to smaller computer centers at each of the major MFE laboratories by a communication network. In addition to providing cost effective computing services, the NMFECC environment stimulates collaboration and the sharing of computer codes among the various fusion research groups

Cell fusions in mammals

DEFF Research Database (Denmark)

Larsson, Lars-Inge; Bjerregaard, Bolette; Talts, Jan Fredrik

2008-01-01

Cell fusions are important to fertilization, placentation, development of skeletal muscle and bone, calcium homeostasis and the immune defense system. Additionally, cell fusions participate in tissue repair and may be important to cancer development and progression. A large number of factors appear...... to regulate cell fusions, including receptors and ligands, membrane domain organizing proteins, proteases, signaling molecules and fusogenic proteins forming alpha-helical bundles that bring membranes close together. The syncytin family of proteins represent true fusogens and the founding member, syncytin-1......, has been documented to be involved in fusions between placental trophoblasts, between cancer cells and between cancer cells and host ells. We review the literature with emphasis on the syncytin family and propose that syncytins may represent universal fusogens in primates and rodents, which work...

Tritium chemistry in fission and fusion reactors

International Nuclear Information System (INIS)

Roth, E.; Masson, M.; Briec, M.

1986-09-01

We are interested in the behaviour of tritium inside the solids where it is generated both in the case of fission nuclear reactor fuel elements, and in that of blankets of future fusion reactor. In the first case it is desirable to be able to predict whether tritium will be found in the hulls or in the uranium oxide, and under what chemical form, in order to take appropriate steps for it's removal in reprocessing plants. In fusion reactors breeding large amounts of tritium and burning it in the plasma should be accomplished in as short a cycle as possible in order to limit inventories that are associated with huge activities. Mastering the chemistry of every step is therefore essential. Amounts generated are not of the same order of magnitude in the two cases studied. Ternary fissions produce about 66 10 13 Bq (18 000 Ci) per year of tritium in a 1000 MWe fission generator, i.e., about 1.8 10 10 Bq (0.5 Ci) per day per ton of fuel

Fusion technologies for Laser Inertial Fusion Energy (LIFE∗

Directory of Open Access Journals (Sweden)

Kramer K.J.

2013-11-01

Full Text Available The Laser Inertial Fusion-based Energy (LIFE engine design builds upon on going progress at the National Ignition Facility (NIF and offers a near-term pathway to commercial fusion. Fusion technologies that are critical to success are reflected in the design of the first wall, blanket and tritium separation subsystems. The present work describes the LIFE engine-related components and technologies. LIFE utilizes a thermally robust indirect-drive target and a chamber fill gas. Coolant selection and a large chamber solid-angle coverage provide ample tritium breeding margin and high blanket gain. Target material selection eliminates the need for aggressive chamber clearing, while enabling recycling. Demonstrated tritium separation and storage technologies limit the site tritium inventory to attractive levels. These key technologies, along with the maintenance and advanced materials qualification program have been integrated into the LIFE delivery plan. This describes the development of components and subsystems, through prototyping and integration into a First Of A Kind power plant.

Fusion reactor wastes

International Nuclear Information System (INIS)

Young, J.R.

1976-01-01

The fusion reactor currently is being developed as a clean source of electricity with an essentially infinite source of fuel. These reactors are visualized as using a fusion reaction to generate large quantities of high temperature energy which can be used as process heat or for the generation of electricity. The energy would be created primarily as the kinetic energy of neutrons or other reaction products. Neutron energy could be converted to high-temperature heat by moderation and capture of the neutrons. The energy of other reaction products could be converted to high-temperature heat by capture, or directly to electricity by direct conversion electrostatic equipment. An analysis to determine the wastes released as a result of operation of fusion power plants is presented

A review of fusion torch applications

International Nuclear Information System (INIS)

Eastlund, B.J.; Gough, W.C.

1983-01-01

The Fusion Torch is a concept developed in 1968 to propose the investigation of non-electrical uses of the flux of particle and electromagnetic radiation capable of being produced from a fusion plasma (leakage). The proposed applications include direct recycling of material, the use of electromagnetic radiation to produce H 2 fuel and novel methods of heat transfer. The purpose of this paper is to review progress, and to discuss ideas that have resulted from new magnetic containment concepts. The practicality of the Fusion Torch concept for direct recycling with D-T fuel cycles was questioned because of neutron-activation. Since 1968, low neutron fusion reactions have received serious consideration. The economics of adding applications features to a fusion reactor must be studied in relation to specific reactor designs. Calculations are presented to illustrate the large advantages applications could offer for low Q, high circulating power systems such as mirrors, small Tokamaks and linear pinches. Little advantage is predicated for high Q, high thermal efficiency systems typified by large Tokamaks. The production of fuels such as H 2 has received study using high temperature electrolysis, radiation chemistry, and thermochemical cycles. Ore reduction using differential ionization is also described. A summary of applications areas are presented along with ideas on the potential of large scale use of such systems

Thermonuclear fusion in the UK: towards a new abundant and durable energy source; La fusion nucleaire au Royaume-Uni: vers une nouvelle source d'energie abondante et durable

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-04-15

The ITER treaty (International thermonuclear experimental reactor) was signed in Paris on November 21, 2006, by the European Union, China, the USA, Japan and Russia. This treaty is devoted to the construction and exploitation of the biggest thermonuclear facility ever, capable to generate 500 MW during a reaction of 10 minutes. ITER is a priori the last experimental step before the construction of a fusion power plant for power generation at the industrial scale. The goal of ITER is to obtain a quasi-unexhaustible and less polluting energy source by the mid-21. century. The British research work has largely contributed to the development of this technology through a large number of projects that have preceded ITER but also through its present day involvement in the creation of the future reactor of Cadarache. This document presents: the UK fusion program, the projects carried out at the Culham science centre (Compass-D, Joint European Torus (JET), Small Tight Aspect Ratio Tokamak (START), Mega-Ampere Spherical Tokamak (MAST), EASY-2005 (European activation system)), the British involvement in ITER project and the transfer of technologies, and the nuclear fusion research in British universities (PPRG Imperial College London, CFSA Warwick university, Dalton nuclear institute (DNI), department of physics York university). (J.S.)

Alignment system for large high-power CO2 laser fusion systems

International Nuclear Information System (INIS)

Bausman, M.D.; Liberman, I.; Manning, J.P.; Singer, S.

1977-01-01

Aligning a pulsed CO 2 laser fusion system involves control systems which insure that the centers of beams follow a prescribed path to within 1 mm, that the pointing of the beams is correct to approximately 20 microradians, and that focal spot at the location of the experimental fusion target be placed to accuracies of 10 to 20 micrometers laterally and approximately 50 micrometers axially. These alignments are accomplished by a variety of sensing techniques which include thermal pinholes and quadrant detectors, Seebeck effect silicon detectors, and imaging autocollimating Hartmann test procedures employing ir vidicon systems

Magnetic mirror fusion: status and prospects

International Nuclear Information System (INIS)

Post, R.F.

1980-01-01

Two improved mirror systems, the tandem mirror (TM) and the field-reversed mirror (FRM) are being intensively studied. The twin practical aims of these studies: to improve the economic prospects for mirror fusion power plants and to reduce the size and/or complexity of such plants relative to earlier approaches to magnetic fusion. While at the present time the program emphasis is still strongly oriented toward answering scientific questions, the emphasis is shifting as the data accumulates and as larger facilities - ones with a heavy technological and engineering orientation - are being prepared. The experimental and theoretical progress that led to the new look in mirror fusion research is briefly reviewed, the new TM and the FRM ideas are outlined, and the projected future course of mirror fusion research is discussed

The European Fusion Programme

International Nuclear Information System (INIS)

Palumbo, D.

1983-01-01

The European Fusion Programme is coordinated by Euratom and represents a long term cooperative project of Member States of the European Communities in the field of fusion, designed to lead to the joint construction of prototypes. The main lines of the programme proposed for 1982 to 1986 are: (1) the continuation of a strong effort on tokamaks with emphasis on JET construction, operation and upgrading, (2) conceptual design of NET and development of the related technology, and (3) further work on two alternative magnetic confinement systems. The current status and future plans for this programme are discussed in the paper. (author)

Hesitant birth of cold fusion

International Nuclear Information System (INIS)

Bockris, J.O.

1992-01-01

John O'M. Bockris, a distinguished chemistry professor at Texas A ampersand M University, finds the reaction to the announcement of the discovery of cold fusion curious. Two years earlier, he notes, there had been a comparable announcement concerning the discovery of high-temperature superconductivity; it received favorable press coverage for months. The cold-fusion announcement, on the other hand, was met with dour skepticism. When other researchers failed in efforts to duplicate the findings of Martin Fleischmann and B. Stanley Pons, Bockris says, the two scientists were held up to ridicule. Bockris says he found a deep emotional opposition to cold fusion, even within his own department and university. This opposition is fueled in large part, he believes, by big science and the hot fusion lobby. A key indicator of cold fusion is the presence of tritium, Brockis claims. At Texas A ampersand M, large amounts of tritium have been found in some experiments; this also has occurred in experiments at more than 40 laboratories in nine countries, he says. Excess heat production is more difficult to attain, he acknowledges. The cold-fusion controversy has uncovered some unflattering characteristics of the scientific community, Bockris says. Among them are: scientists are no less driven by emotion that business people or politicians; research funding decisions serve to perpetuate the goals of politically powerful interest groups; and ideas have great inertia once planted in a scientist's mind

Advanced fission and fossil plant economics-implications for fusion

International Nuclear Information System (INIS)

Delene, J.G.

1994-01-01

In order for fusion energy to be a viable option for electric power generation, it must either directly compete with future alternatives or serve as a reasonable backup if the alternatives become unacceptable. This paper discusses projected costs for the most likely competitors with fusion power for baseload electric capacity and what these costs imply for fusion economics. The competitors examined include advanced nuclear fission and advanced fossil-fired plants. The projected costs and their basis are discussed. The estimates for these technologies are compared with cost estimates for magnetic and inertial confinement fusion plants. The conclusion of the analysis is that fusion faces formidable economic competition. Although the cost level for fusion appears greater than that for fission or fossil, the costs are not so high as to preclude fusion's potential competitiveness

Fusion power and the environment

International Nuclear Information System (INIS)

Holdren, J.P.; Fowler, T.K.; Post, R.F.

1975-01-01

Environmental characteristics of conceptual fusion-reactor systems based on magnetic confinement are examined quantitatively, and some comparisons with fission systems are made. Fusion, like all other energy sources, will not be completely free of environmental liabilities, but the most obvious of these--tritium leakage and activation of structural materials by neutron bombardment--are susceptible to significant reduction by ingenuity in choice of materials and design. Large fusion reactors can probably be designed so that worst-case releases of radioactivity owing to accident or sabotage would produce no prompt fatalities in the public. A world energy economy relying heavily on fusion could make heavy demands on scarce nonfuel materials, a topic deserving further attention. Fusion's potential environmental advantages are not entirely ''automatic'', converting them into practical reality will require emphasis on environmental characteristics throughout the process of reactor design and engineering. The central role of environmental impact in the long-term energy dilemma of civilization justifies the highest priority on this aspect of fusion

The assessment of fusion power

International Nuclear Information System (INIS)

Bickerton, Roy

1990-01-01

It is argued that the recent 'Science and Technology Options Assessments' of fusion power produced for the European Parliament is incorrecta and misleading. The report takes no account of the complex organizational structure of the European fusion programme, it misrepresents history, and it presents incomprehensible graphical evidence and criteria which are narrowly-based and largely platitudinous. (author)

Fusion research at Imperial College

International Nuclear Information System (INIS)

Haines, M.G.

1990-01-01

The historical roots of fusion research at Imperial College can be traced back to 1946 with the pioneering work of G.P. Thomson. At present research in fusion is carried out in several research groups with interdisciplinary work managed by the Centre for Fusion Studies. The principal research activity will be centred on a newly funded 5 TW pulsed power facility allowing an experimental and theoretical study of radiation collapse and fusion conditions in the dense Z-pinch. Laser-plasma studies relevant to inertial confinement are carried out using the Rutherford-Appleton Laboratory's Central Laser Facility and the new ultra-short pulse (300 fs) laser facility at Imperial College. There is a significant collaboration on the Joint European Torus and the Next European Torus together with a continuation of a long association with Culham Laboratory. Several European collaborations funded by the Comission of the European Communities and other world-wide collaborations form an integral part of this university programme, which is by far the largest in the UK. After a sketch of the historical development of fusion activities, the current and future programme of fusion research at Imperial College is presented in each of the three broad areas: the Z-pinch, laser-driven inertial confinement fusion and tokamak and other conventional magnetic confinement schemes. A summary of the funding and collaborations is outlined. (author)

Perspective on the fusion-fission energy concept

International Nuclear Information System (INIS)

Liikala, R.C.; Perry, R.T.; Teofilo, V.L.

1978-01-01

A concept which has potential for near-term application in the electric power sector of our energy economy is combining fusion and fission technology. The fusion-fission system, called a hybrid, is distinguished from its pure fusion counterpart by incorporation of fertile materials (uranium or thorium) in the blanket region of a fusion machine. The neutrons produced by the fusion process can be used to generate energy through fission events in the blanket or produce fuel for fission reactors through capture events in the fertile material. The performance requirements of the fusion component of hybrids is perceived as being less stringent than those for pure fusion electric power plants. The performance requirements for the fission component of hybrids is perceived as having been demonstrated or could be demonstrated with a modest investment of research and development funds. This paper presents our insights and observations of this concept in the context of why and where it might fit into the picture of meeting our future energy needs. A bibliography of hybrid research is given

Future developments of power supply from nuclear fission and fusion until the middle of the 21st century

International Nuclear Information System (INIS)

1987-03-01

The purpose of this study made by General Technology Systems (Netherlands) is to provide information about nuclear fission and fusion as methods for power generation, with which, in the framework of a study into the possibilities of durable energy sources, choices may be made from the various possibilities for future energy supply. The physical processes upon which the power generation relies are treated briefly. The technologies employed are discussed together with their changes and improvements, now and in the future, and the economic factors by which they are accompanied. How much of this energy will be used in the Netherlands, is discussed. In order to know the opinion of others about these subjects the dealers of the current nuclear power stations were asked to give their opinions which are collected in a supplement. 166 refs.; 18 figs.; 19 tabs

The yeast cell fusion protein Prm1p requires covalent dimerization to promote membrane fusion.

Directory of Open Access Journals (Sweden)

Alex Engel

2010-05-01

Full Text Available Prm1p is a multipass membrane protein that promotes plasma membrane fusion during yeast mating. The mechanism by which Prm1p and other putative regulators of developmentally controlled cell-cell fusion events facilitate membrane fusion has remained largely elusive. Here, we report that Prm1p forms covalently linked homodimers. Covalent Prm1p dimer formation occurs via intermolecular disulfide bonds of two cysteines, Cys-120 and Cys-545. PRM1 mutants in which these cysteines have been substituted are fusion defective. These PRM1 mutants are normally expressed, retain homotypic interaction and can traffic to the fusion zone. Because prm1-C120S and prm1-C545S mutants can form covalent dimers when coexpressed with wild-type PRM1, an intermolecular C120-C545 disulfide linkage is inferred. Cys-120 is adjacent to a highly conserved hydrophobic domain. Mutation of a charged residue within this hydrophobic domain abrogates formation of covalent dimers, trafficking to the fusion zone, and fusion-promoting activity. The importance of intermolecular disulfide bonding informs models regarding the mechanism of Prm1-mediated cell-cell fusion.

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

The scientific status of fusion

International Nuclear Information System (INIS)

Crandall, D.H.

1989-01-01

The development of fusion energy has been a large-scale scientific undertaking of broad interest. The magnetic plasma containment in tokamaks and the laser-drive ignition of microfusion capsules appear to be scientifically feasible sources of energy. These concepts are bounded by questions of required intensity in magnetid field and plasma currents or in drive energy and, for both concepts, by issues of plasma stability and energy transport. The basic concept and the current scientific issues are described for magnetic fusion and for the interesting, but likely infeasible, muon-catalyzed fusion concept. Inertial fusion is mentioned, qualitatively, to complete the context. For magnetic fusion, the required net energy production within the plasma may be accomplished soon, but the more useful goal of self-sustained plasma ignition requires a new device of somewhat uncertain (factor of 2) cost and size. (orig.)

Structural Transition and Antibody Binding of EBOV GP and ZIKV E Proteins from Pre-Fusion to Fusion-Initiation State

Directory of Open Access Journals (Sweden)

Anna Lappala

2018-05-01

Full Text Available Membrane fusion proteins are responsible for viral entry into host cells—a crucial first step in viral infection. These proteins undergo large conformational changes from pre-fusion to fusion-initiation structures, and, despite differences in viral genomes and disease etiology, many fusion proteins are arranged as trimers. Structural information for both pre-fusion and fusion-initiation states is critical for understanding virus neutralization by the host immune system. In the case of Ebola virus glycoprotein (EBOV GP and Zika virus envelope protein (ZIKV E, pre-fusion state structures have been identified experimentally, but only partial structures of fusion-initiation states have been described. While the fusion-initiation structure is in an energetically unfavorable state that is difficult to solve experimentally, the existing structural information combined with computational approaches enabled the modeling of fusion-initiation state structures of both proteins. These structural models provide an improved understanding of four different neutralizing antibodies in the prevention of viral host entry.

Mirror Fusion Test Facility: an intermediate device to a mirror fusion reactor

International Nuclear Information System (INIS)

Karpenko, V.N.

1983-01-01

The Mirror Fusion Test Facility (MFTF-B) now under construction at Lawrence Livermore National Laboratory represents more than an order-of-magnitude step from earlier magnetic-mirror experiments toward a future mirror fusion reactor. In fact, when the device begins operating in 1986, the Lawson criteria of ntau = 10 14 cm -3 .s will almost be achieved for D-T equivalent operation, thus signifying scientific breakeven. Major steps have been taken to develop MFTF-B technologies for tandem mirrors. Steady-state, high-field, superconducting magnets at reactor-revelant scales are used in the machine. The 30-s beam pulses, ECRH, and ICRH will also introduce steady-state technologies in those systems

Radiological design criteria for fusion power test facilities

International Nuclear Information System (INIS)

Singh, M.S.; Campbell, G.W.

1982-01-01

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

Utility requirements for fusion power

International Nuclear Information System (INIS)

DeBellis, R.J.

1977-03-01

A four-man month study was undertaken to identify utility requirements of fusion power and define a role for the utilities in the fusion development process during the 1980s. This report, preliminary in nature, serves mainly as a planning document for future requirements analyses. A requirements organization was defined to consist of three major chronological phases: research and development, plant installation, and plant operation. Thirty-seven requirements were identified, covering all categories. In addition, training, environment, safety, licensing, and utility model were identified as five matrix-type requirements. As the requirement definition process continued during the study period, comments received from utility representatives revealed a consistency of key issues in the fusion development process. These issues form the basis for the eventual establishment of definitive roles for the utilities during the 1980s. The issues are not meant to reflect a negative view of fusion, but are items that must be solved before fusion can be introduced commercially as an electrical power source. As a result of this requirements study, preliminary candidate roles for the utilities in the fusion development process during the 1980s were identified as public education, commercialization studies, industry investment analyses, training plan implementation, alternate reactor concept development, ERDA concept design review, and requirements refinement

Large-Scale, Parallel, Multi-Sensor Data Fusion in the Cloud

Science.gov (United States)

Wilson, B. D.; Manipon, G.; Hua, H.

2012-12-01

NASA's Earth Observing System (EOS) is an ambitious facility for studying global climate change. The mandate now is to combine measurements from the instruments on the "A-Train" platforms (AIRS, AMSR-E, MODIS, MISR, MLS, and CloudSat) and other Earth probes to enable large-scale studies of climate change over periods of years to decades. However, moving from predominantly single-instrument studies to a multi-sensor, measurement-based model for long-duration analysis of important climate variables presents serious challenges for large-scale data mining and data fusion. For example, one might want to compare temperature and water vapor retrievals from one instrument (AIRS) to another instrument (MODIS), and to a model (ECMWF), stratify the comparisons using a classification of the "cloud scenes" from CloudSat, and repeat the entire analysis over years of AIRS data. To perform such an analysis, one must discover & access multiple datasets from remote sites, find the space/time "matchups" between instruments swaths and model grids, understand the quality flags and uncertainties for retrieved physical variables, assemble merged datasets, and compute fused products for further scientific and statistical analysis. To efficiently assemble such decade-scale datasets in a timely manner, we are utilizing Elastic Computing in the Cloud and parallel map/reduce-based algorithms. "SciReduce" is a Hadoop-like parallel analysis system, programmed in parallel python, that is designed from the ground up for Earth science. SciReduce executes inside VMWare images and scales to any number of nodes in the Cloud. Unlike Hadoop, in which simple tuples (keys & values) are passed between the map and reduce functions, SciReduce operates on bundles of named numeric arrays, which can be passed in memory or serialized to disk in netCDF4 or HDF5. Thus, SciReduce uses the native datatypes (geolocated grids, swaths, and points) that geo-scientists are familiar with. We are deploying within Sci

General description of preliminary design of an experimental fusion reactor and the future problems

International Nuclear Information System (INIS)

Sako, Kiyoshi

1976-01-01

Recently, the studies on plasma physics has progressed rapidly, and promising experimental data emerged successively. Especially expectation mounts high that Tokamak will develop into power reactors. In Japan, the construction of large plasma devices such as JT-60 of JAERI is going to start, and after several years, the studies on plasma physics will come to the end of first stage, then the main research and development will be directed to power reactors. The studies on the design of practical fusion reactors have been in progress since 1973 in JAERI, and the preliminary design is being carried out. The purposes of the preliminary design are the clarification of the concept of the experimental reactor and the requirements for the studies on core plasma, the examination of the problems for developing main components and systems of the reactor, and the development of design technology. The experimental reactor is the quasi-steady reactor of 100 MW fusion reaction output, and the conditions set for the design and the basis of their setting are explained. The outline of the design, namely core plasma, blankets, superconductive magnets and the shielding with them, vacuum wall, neutral particle injection heating device, core fuel supply and exhaust system, and others, is described. In case of scale-up the reactor structural material which can withstand neutron damage must be developed. (Kako, I.)

Nuclear fusion research and plasma application technologies in SWIP (Southwestern Institute of Physics)

International Nuclear Information System (INIS)

Deng, X.W.

1990-01-01

A brief introduction of nuclear fusion research and plasma application technologies in SWIP is reported in this paper. The SWIP focuses its fusion efforts mainly on Tokamak with mirror as the supplemental experiments and fusion reactor conceptual design as preparation for future application of fusion energy. SWIP is making great efforts on fusion technology spin-off to make contribution towards national economic construction. (Author)

Nuclear fusion - Inexhaustible source of energy for tomorrow

International Nuclear Information System (INIS)

Leiser, M.; Demchenko, V.

1989-09-01

The purpose of this paper is to provide a general description of nuclear fusion as an energy option for the future and to clarify to some extent the various issues - scientific, technological, economic and environmental - which are likely to be relevant to controlled thermonuclear fusion. Section 1 describes the world energy problem and some advantages of nuclear fusion compared to other energy options. Sections 2 and 3 describe the fundamentals of fusion energy, plasma confinement, heating and technological aspects of fusion researches. Some plasma confinement schemes (tokamak, stellarator, inertial confinement fusion) are described. The main experimental results and parameter devices are cited to illustrate the state of the art as of 1989. Various engineering problems associated with reactor design, magnetic systems, materials, plasma purity, fueling, blankets, environment, economics and safety are discussed. A description of both bilateral and multilateral efforts in fusion research under the auspices of the IAEA is presented in Section 4. (author). 11 refs, 4 figs, 1 tab

Large potassium dihydrogen phosphate crystal growth using a three-vessel system for fusion lasers

International Nuclear Information System (INIS)

Sasaki, T.; Yokotani, A.; Yamanaka, T.; Nakai, S.; Yamanaka, C.

1989-01-01

Large scale laser fusion experiments are being performed in the Institute of Laser Engineering, Osaka University, using the glass laser system Gekko-XII. For this laser, very large nonlinear crystals of potassium dihydrogen phosphate (KDP) with a cross section over 40 X 40 cm is needed as a frequency converter to obtain a short wavelength laser. Generally the temperature falling method (TFM) is used to grow such a huge crystal, but the volume of the growing vessel becomes tremendously large. The three-vessel system (TVS), which is a constant temperature and concentration method, allows better control of supersaturation than does the TFM, and the volume of the main growth vessel can be smaller than that in the case of the TFM. The authors have constructed a TVS. The KDP crystal grew in the growth tank that was kept at a constant temperature of 20 +- 0.01 0 C. The authors show the growth history of the KDP crystal of a 40- X 40-cm cross section. This system is now being operated to obtain the KDP of 100-cm height, and a theoretical estimate of the growth rate is under consideration. These results are presented

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

The recent progress of laser fusion research and future scope

International Nuclear Information System (INIS)

Yamanaka, C.

1986-01-01

The plasma compression of spherical fuel pellets is performed by irradiation laser beams on the surface of targets. The short wavelength laser or Xray is effective to get high coupling of laser and plasmas without preheating. The implosion uniformity is essentially important to attain the high compression. As for the direct implosion, the multibeam irradiation is necessary to keep a good uniformity of illumination. Extremely high aspect ratio targets are successfully imploded withy neutron yield 10/sup 12/ or more. The shock wave multiplexing is introduced by tailored laser pulses synchronizing with the compression stagnation. Implosion instability seems to be prevented by this scheme. Energy recovering by nuclear fusion is about 10/sup -3/ of the incident laser beam. The indirect implosion using the Cannonball target is very effective to keep the high absorption and the implosion uniformity. However the suprathermal electrons are increased especially at the region of the beam inlet holes. The larger cavity irradiated by the shorter wavelength laser indicates the better results. The Xray conversion by laser is intensively studied using metal targets. Magnetically Insulated Inetially Confined Fusion (MICF) is tested by using CO/sub 2/ lasers. The basic structure of the MICF target is a double shell structure. The irradiation of laser beams through holes of the outer shell produces a toroidal magnetic field due to the current loop produced by the ejected hot electrons. Self organized magnetic field is expected to confine the plasma energy. Plasmas are preserved by the inertial confinement scheme. The experimental results are very interesting to design a hybrid fusion device

The role of improved fusion concepts

International Nuclear Information System (INIS)

Nelson, D.B.; Linford, R.K.; Liu, C.S.; Logan, B.G.; Rose, P.H.

1985-01-01

The U.S. Dept. of Energy discusses concept improvement in the tokamak and concept improvement in the mirror. Controlled Thermonuclear Research comments on what constitutes an attractive fusion reactor, and provides a table of achieved parameters of RFP, FRC and the spheromak experiments. GA Technologies Inc. remarks on the direction which industry must take in the fusion program. The Lawrence Livermore National Laboratory concentrates on commercial reactor studies. Spectra Technology focuses on problems dealing with fusion proponents making a convincing and clear economic argument for fusion based on a mils per kilowat basis, and the large costs of flagship experiments. The Oak Ridge National Laboratory remarks on the need for an economic energy source for fusion. A table of cost of electricity contours is shown

The role of improved fusion concepts

Energy Technology Data Exchange (ETDEWEB)

Nelson, D.B.; Linford, R.K.; Liu, C.S.; Logan, B.G.; Rose, P.H.

1985-06-01

The U.S. Dept. of Energy discusses concept improvement in the tokamak and concept improvement in the mirror. Controlled Thermonuclear Research comments on what constitutes an attractive fusion reactor, and provides a table of achieved parameters of RFP, FRC and the spheromak experiments. GA Technologies Inc. remarks on the direction which industry must take in the fusion program. The Lawrence Livermore National Laboratory concentrates on commercial reactor studies. Spectra Technology focuses on problems dealing with fusion proponents making a convincing and clear economic argument for fusion based on a mils per kilowat basis, and the large costs of flagship experiments. The Oak Ridge National Laboratory remarks on the need for an economic energy source for fusion. A table of cost of electricity contours is shown.

External events analysis for experimental fusion facilities

International Nuclear Information System (INIS)

Cadwallader, L.C.

1990-01-01

External events are those off-normal events that threaten facilities either from outside or inside the building. These events, such as floods, fires, and earthquakes, are among the leading risk contributors for fission power plants, and the nature of fusion facilities indicates that they may also lead fusion risk. This paper gives overviews of analysis methods, references good analysis guidance documents, and gives design tips for mitigating the effects of floods and fires, seismic events, and aircraft impacts. Implications for future fusion facility siting are also discussed. Sites similar to fission plant sites are recommended. 46 refs

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

Information Fusion of Conflicting Input Data

Directory of Open Access Journals (Sweden)

Uwe Mönks

2016-10-01

Full Text Available Sensors, and also actuators or external sources such as databases, serve as data sources in order to realise condition monitoring of industrial applications or the acquisition of characteristic parameters like production speed or reject rate. Modern facilities create such a large amount of complex data that a machine operator is unable to comprehend and process the information contained in the data. Thus, information fusion mechanisms gain increasing importance. Besides the management of large amounts of data, further challenges towards the fusion algorithms arise from epistemic uncertainties (incomplete knowledge in the input signals as well as conflicts between them. These aspects must be considered during information processing to obtain reliable results, which are in accordance with the real world. The analysis of the scientific state of the art shows that current solutions fulfil said requirements at most only partly. This article proposes the multilayered information fusion system MACRO (multilayer attribute-based conflict-reducing observation employing the μBalTLCS (fuzzified balanced two-layer conflict solving fusion algorithm to reduce the impact of conflicts on the fusion result. The performance of the contribution is shown by its evaluation in the scope of a machine condition monitoring application under laboratory conditions. Here, the MACRO system yields the best results compared to state-of-the-art fusion mechanisms. The utilised data is published and freely accessible.

Information Fusion of Conflicting Input Data.

Science.gov (United States)

Mönks, Uwe; Dörksen, Helene; Lohweg, Volker; Hübner, Michael

2016-10-29

Sensors, and also actuators or external sources such as databases, serve as data sources in order to realise condition monitoring of industrial applications or the acquisition of characteristic parameters like production speed or reject rate. Modern facilities create such a large amount of complex data that a machine operator is unable to comprehend and process the information contained in the data. Thus, information fusion mechanisms gain increasing importance. Besides the management of large amounts of data, further challenges towards the fusion algorithms arise from epistemic uncertainties (incomplete knowledge) in the input signals as well as conflicts between them. These aspects must be considered during information processing to obtain reliable results, which are in accordance with the real world. The analysis of the scientific state of the art shows that current solutions fulfil said requirements at most only partly. This article proposes the multilayered information fusion system MACRO (multilayer attribute-based conflict-reducing observation) employing the μ BalTLCS (fuzzified balanced two-layer conflict solving) fusion algorithm to reduce the impact of conflicts on the fusion result. The performance of the contribution is shown by its evaluation in the scope of a machine condition monitoring application under laboratory conditions. Here, the MACRO system yields the best results compared to state-of-the-art fusion mechanisms. The utilised data is published and freely accessible.

Social assessment on fusion energy technology

International Nuclear Information System (INIS)

Nemoto, Kazuyasu

1981-01-01

In regard to the research and development for fusion energy technologies which are still in the stage of demonstrating scientific availability, it is necessary to accumulate the demonstrations of economic and environmental availability through the demonstration of technological availability. The purpose of this report is to examine how the society can utilize the new fusion energy technology. The technical characteristics of fusion energy system were analyzed in two aspects, namely the production techniques of thermal energy and electric energy. Also on the social characteristics in the fuel cycle stage of fusion reactors, the comparative analysis with existing fission reactors was carried out. Then, prediction and evaluation were made what change of social cycle fusion power generation causes on the social system formalized as a socio-ecological model. Moreover, the restricting factors to be the institutional obstacles to the application of fusion energy system to the society were analyzed from three levels of the decision making on energy policy. Since the convertor of fusion energy system is steam power generation system similar to existing system, the contents and properties of the social cycle change in the American society to which such new energy technology is applied are not much different even if the conversion will be made in future. (Kako, I.)

Heavy ion inertial fusion

International Nuclear Information System (INIS)

Keefe, D.; Sessler, A.M.

1980-01-01

Inertial fusion has not yet been as well explored as magnetic fusion but can offer certain advantages as an alternative source of electric energy for the future. Present experiments use high-power beams from lasers and light-ion diodes to compress the deuterium-tritium (D-T) pellets but these will probably be unsuitable for a power plant. A more promising method is to use intense heavy-ion beams from accelerator systems similar to those used for nuclear and high-energy physics; the present paper addresses itself to this alternative. As will be demonstrated the very high beam power needed poses new design questions, from the ion-source through the accelerating system, the beam transport system, to the final focus. These problems will require extensive study, both theoretically and experimentally, over the next several years before an optimum design for an inertial fusion driver can be arrived at. (Auth.)

Heavy ion inertial fusion

International Nuclear Information System (INIS)

Keefe, D.; Sessler, A.M.

1980-07-01

Inertial fusion has not yet been as well explored as magnetic fusion but can offer certain advantages as an alternative source of electric energy for the future. Present experiments use high-power beams from lasers and light-ion diodes to compress the deuterium-tritium (D-T) pellets but these will probably be unsuitable for a power plant. A more promising method is to use intense heavy-ion beams from accelerator systems similar to those used for nuclear and high-energy physics; the present paper addresses itself to this alternative. As will be demonstrated the very high beam power needed poses new design questions, from the ion source through the accelerating system, the beam transport system, to the final focus. These problems will require extensive study, both theoretically and experimentally, over the next several years before an optimum design for an inertial fusion driver can be arrived at

High-Energy Physics Strategies and Future Large-Scale Projects

CERN Document Server

Zimmermann, F

2015-01-01

We sketch the actual European and international strategies and possible future facilities. In the near term the High Energy Physics (HEP) community will fully exploit the physics potential of the Large Hadron Collider (LHC) through its high-luminosity upgrade (HL-LHC). Post-LHC options include a linear e+e- collider in Japan (ILC) or at CERN (CLIC), as well as circular lepton or hadron colliders in China (CepC/SppC) and Europe (FCC). We conclude with linear and circular acceleration approaches based on crystals, and some perspectives for the far future of accelerator-based particle physics.

Cold fusion catalyzed by muons and electrons

International Nuclear Information System (INIS)

Kulsrud, R.M.

1990-10-01

Two alternative methods have been suggested to produce fusion power at low temperature. The first, muon catalyzed fusion or MCF, uses muons to spontaneously catalyze fusion through the muon mesomolecule formation. Unfortunately, this method fails to generate enough fusion energy to supply the muons, by a factor of about ten. The physics of MCF is discussed, and a possible approach to increasing the number of MCF fusions generated by each muon is mentioned. The second method, which has become known as ''Cold Fusion,'' involves catalysis by electrons in electrolytic cells. The physics of this process, if it exists, is more mysterious than MCF. However, it now appears to be an artifact, the claims for its reality resting largely on experimental errors occurring in rather delicate experiments. However, a very low level of such fusion claimed by Jones may be real. Experiments in cold fusion will also be discussed

Trends of researches for fusion engineering research facility (FERF)

International Nuclear Information System (INIS)

Ozawa, Yasutomo; Enoto, Takeaki

1975-01-01

The role of a fusion neutron radiation test facility in the development of a scientific feasibility experimental reactor or demonstration fusion power reactor plant would be analogous to the role of the materials testing and experimental reactors in the development of fission power reactor. While the material testing fission reactor has been developed after successful operation of fission reactors, in the case of fusion reactor development it is desirable to realize the fusion engineering research facility (FERF) in-phase to the development of SFX and/or demonstration fusion power reactor plants. Here so called FERF in near future is the Controlled Thermonuclear Reactor which provides the high-intensity and high-energy neutron and plasma source whether the net power output is produced or not. From the point of direct attainment to SFX, we would like to emphasize that FEFE is the royal road leading to the goal of successful achievement of CTR program and could be useful for the experiment on impurity effects caused by neutron and plasma irradiations onto the wall material for SFX. Further, we rather suppose that hybrid FERF-fission assembly could be fairly and easily realizable in near future. (auth.)

Tritium experience in the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Skinner, C.H.; Blanchard, W.; Hosea, J.; Mueller, D.; Nagy, A.; Hogan, J.

1998-01-01

Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 years of successful deuterium-tritium (D-T) operations in the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory. The D-T campaign enabled TFTR to explore the transport, alpha physics, and MHD stability of a reactor core. It also provided experience with tritium retention and removal that highlighted the importance of these issues in future D-T machines. In this paper, the authors summarize the tritium retention and removal experience in TFTR and its implications for future reactors

Neutronic Parametric Study on a Conceptual Design for a Transmutation Fusion Blanket

International Nuclear Information System (INIS)

Tariq Siddique, M.; Kim, Myung Hyun

2011-01-01

Fusion energy may be the one of options of future energy. In all over the world, researchers are putting their efforts for its commercial and economical availability. Fusion-fission hybrid reactors have been studied for various applications in China. First milestone of fusion energy is expected to be the fusion fission hybrid reactors. In fusion-fission hybrid reactor the blanket design is of second prime importance after fusion source. In this study conceptual design of a fusion blanket is initiated for calculation of tritium production, transmutation of minor actinides (MA) and fission products (FP) and energy multiplication calculations

Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Perry, E.; Chrzanowski, J.; Rule, K.; Viola, M.; Williams, M.; Strykowsky, R.

1999-01-01

The Tokamak Fusion Test Reactor (TFTR) is a one-of-a-kind, tritium-fueled fusion research reactor that ceased operation in April 1997. The Decontamination and Decommissioning (D and D) of the TFTR is scheduled to occur over a period of three years beginning in October 1999. This is not a typical Department of Energy D and D Project where a facility is isolated and cleaned up by ''bulldozing'' all facility and hardware systems to a greenfield condition. The mission of TFTR D and D is to: (a) surgically remove items which can be re-used within the DOE complex, (b) remove tritium contaminated and activated systems for disposal, (c) clear the test cell of hardware for future reuse, (d) reclassify the D-site complex as a non-nuclear facility as defined in DOE Order 420.1 (Facility Safety) and (e) provide data on the D and D of a large magnetic fusion facility. The 100 cubic meter volume of the donut-shaped reactor makes it the second largest fusion reactor in the world. The record-breaking deuterium-tritium experiments performed on TFTR resulted in contaminating the vacuum vessel with tritium and activating the materials with 14 Mev neutrons. The total tritium content within the vessel is in excess of 7,000 Curies while dose rates approach 75 mRem/hr. These radiological hazards along with the size and shape of the Tokamak present a unique and challenging task for dismantling

Research program. Controlled thermonuclear fusion. Synthesis report 2014

International Nuclear Information System (INIS)

Villard, L.; Marot, L.; Fiocco, D.

2015-01-01

In 1961, 3 years after the 2 nd International Conference on Peaceful Use of Nuclear Energy, the Research Centre on Plasma Physics (CRPP) was created as a department of the Federal Institute of Technology (EPFL) in Lausanne (Switzerland). From 1979, CRPP collaborates to the European Program on fusion research in the framework of EURATOM. The advantages of fusion are remarkable: the fuel is available in great quantity all over the world; the reactor is intrinsically safe; the reactor material, activated during operation, loses practically all its activity within about 100 years. But the working up of the controlled fusion necessitates extreme technological conditions. In 1979, the Joint European Torus (JET) began its operation; today it is still the most powerful tokamak in the world; its energy yield Q reached 0.65. The progress realized in the framework of EURATOM has led to the planning of the experimental reactor ITER which is being built at Cadarache (France). ITER is designed to reach a Q-value largely above 1. The future prototype reactor DEMO is foreseen in 2040-2050. It should demonstrate the ability of a fusion reactor to inject electricity into the grid for long term. In 2014, CRPP participated in the works on ITER in the framework of the Fusion for Energy (F4E) agency. At EPFL the research concerns the physics of the magnetic confinement with experiments on the tokamak TCV (variable configuration tokamak), the numerical simulations, the plasma heating and the generation of current by hyper frequency radio waves. At the Paul Scherrer Institute (PSI), research is devoted to the superconductivity. At the Basel University the studies get on interactions between the plasma and the tokamak walls. The large flexibility of TCV allows creating and controlling plasmas of different shapes which are necessary to optimise the core geometry of future reactors. Moreover, the plasma heating by mm radio waves allows guiding the injected power according to specific

Major achievements and challenges of fusion research

International Nuclear Information System (INIS)

Tendler, Michael

2015-01-01

The ITER project is truly at the frontier of knowledge, a collective effort to explore the tantalizing future of free, clean and inexhaustible energy offered by nuclear fusion. Where the Large Hadron Collider at CERN pushes the boundaries of physics to find the origins of matter, the ITER Project seeks to give humans an endless stream of power which could have potentially game-changing consequences for the entire planet. Seminal contributions to the general physics knowledge accomplished by the plasma physics research for the benefit of the ITER project will be brought to light. The legacy of Professor H Alfvén within the framework of the ITER project will be described. (invited comment)

Fusion-bonded fluidic interconnects

International Nuclear Information System (INIS)

Fazal, I; Elwenspoek, M C

2008-01-01

A new approach to realize fluidic interconnects based on the fusion bonding of glass tubes with silicon is presented. Fusion bond strength analyses have been carried out. Experiments with plain silicon wafers and coated with silicon oxide and silicon nitride are performed. The obtained results are discussed in terms of the homogeneity and strength of fusion bond. High pressure testing shows that the bond strength is large enough for most applications of fluidic interconnects. The bond strength for 525 µm thick silicon, with glass tubes having an outer diameter of 6 mm and with a wall thickness of 2 mm, is more than 60 bars after annealing at a temperature of 800 °C

Catalogue of nuclear fusion codes - 1976

International Nuclear Information System (INIS)

1976-10-01

A catalogue is presented of the computer codes in nuclear fusion research developed by JAERI, Division of Thermonuclear Fusion Research and Division of Large Tokamak Development in particular. It contains a total of about 100 codes under the categories: Atomic Process, Data Handling, Experimental Data Processing, Engineering, Input and Output, Special Languages and Their Application, Mathematical Programming, Miscellaneous, Numerical Analysis, Nuclear Physics, Plasma Physics and Fusion Research, Plasma Simulation and Numerical Technique, Reactor Design, Solid State Physics, Statistics, and System Program. (auth.)

Complete fusion in light 'heavy ion' collisions

International Nuclear Information System (INIS)

Volant, C.; Wieleczko, J.P.

1979-01-01

In the last few years a large amount of data have been obtained on the complete fusion of light ions. One of the aim of these studies was to look for aspects which could not be explained by the macroscopic description of the fusion which works quite well for heavier systems. Indeed, it was suggested that for light systems the fusion could be sometimes limited by compound nucleus properties or by some particular structures in the entrance channel. In this talk new results on fusion experiments obtained by the Saclay group are presented

Advanced smart tungsten alloys for a future fusion power plant

Science.gov (United States)

Litnovsky, A.; Wegener, T.; Klein, F.; Linsmeier, Ch; Rasinski, M.; Kreter, A.; Tan, X.; Schmitz, J.; Mao, Y.; Coenen, J. W.; Bram, M.; Gonzalez-Julian, J.

2017-06-01

The severe particle, radiation and neutron environment in a future fusion power plant requires the development of advanced plasma-facing materials. At the same time, the highest level of safety needs to be ensured. The so-called loss-of-coolant accident combined with air ingress in the vacuum vessel represents a severe safety challenge. In the absence of a coolant the temperature of the tungsten first wall may reach 1200 °C. At such a temperature, the neutron-activated radioactive tungsten forms volatile oxide which can be mobilized into atmosphere. Smart tungsten alloys are being developed to address this safety issue. Smart alloys should combine an acceptable plasma performance with the suppressed oxidation during an accident. New thin film tungsten-chromium-yttrium smart alloys feature an impressive 105 fold suppression of oxidation compared to that of pure tungsten at temperatures of up to 1000 °C. Oxidation behavior at temperatures up to 1200 °C, and reactivity of alloys in humid atmosphere along with a manufacturing of reactor-relevant bulk samples, impose an additional challenge in smart alloy development. First exposures of smart alloys in steady-state deuterium plasma were made. Smart tungsten-chroimium-titanium alloys demonstrated a sputtering resistance which is similar to that of pure tungsten. Expected preferential sputtering of alloying elements by plasma ions was confirmed experimentally. The subsequent isothermal oxidation of exposed samples did not reveal any influence of plasma exposure on the passivation of alloys.

Fusion-reactor blanket and coolant material compatibility

International Nuclear Information System (INIS)

Jeppson, D.W.; Keough, R.F.

1981-01-01

Fusion reactor blanket and coolant compatibility tests are being conducted to aid in the selection and design of safe blanket and coolant systems for future fusion reactors. Results of scoping compatibility tests to date are reported for blanket material and water interactions at near operating temperatures. These tests indicate the quantitative hydrogen release, the maximum temperature and pressures produced and the rates of interactions for selected blanket materials

Inertial fusion by laser

International Nuclear Information System (INIS)

Dautray, R.; Watteau, J.-P.

1980-01-01

Following a brief historical survey of research into the effects of interaction of laser with matter, the principles of fusion by inertial confinement are described and the main parameters and possible levels given. The development of power lasers is then discussed with details of performances of the main lasers used in various laboratories, and with an assessment of the respective merits of neodymium glass, carbon dioxide or iodine lasers. The phenomena of laser radiation and its interaction with matter is then described, with emphasis on the results of experiments concerned with target implosion with the object of compressing and heating the mixture of heavy hydrogen and tritium to be ignited. Finally, a review is made of future possibilities opened up by the use of large power lasers which have recently become operational or are being constructed, and the ground still to be covered before a reactor can be produced [fr

Summary of existing superconducting magnet experience and its relevance to the safety of fusion magnet

International Nuclear Information System (INIS)

Hsieh, S.Y.; Allinger, J.; Danby, G.; Keane, J.; Powell, J.; Prodell, A.

1975-01-01

A comprehensive summary of experience with over twenty superconducting magnet systems has been collected through visits to and discussions about existing facilities including, for example, the bubble chamber magnets at Brookhaven National Laboratory, Argonne National Laboratory and Fermi National Accelerator Laboratory, and the large superconducting spectrometer at Stanford Linear Accelerator Center. This summary includes data relating to parameters of these magnets, magnet protection methods, and operating experiences. The information received is organized and presented in the context of its relevance to the safe operation of future, very large superconducting magnet systems for fusion power plants

Science or Fiction - Is there a Future for Nuclear

International Nuclear Information System (INIS)

Wenisch, A.; Kromp, R.; Reinberger, D.

2007-01-01

This booklet served as preparation for both participants and speakers at the conference »Science or Fiction – Is there a Future for Nuclear?«. This international conference on fusion energy and new nuclear reactor models was organized by Global 2000/Friends of the Earth Austria and took place 8 November 2007 in Vienna. This booklet contains our contribution to the ongoing discussion about future energy security and what paths we should take. We focus on the possible future scenarios for nuclear power. The nuclear industry is trying to secure its own future by reintroducing old concepts like nuclear fusion and updating old fission reactors in so-called Generation IV systems. While there is enough information available on both fission and fusion energy from project financiers, research institutions and the European Commission, who gave the lion share of energy research funds into fusion research, we attempt here to provide a broader perspective and examine how much is Fiction and what these concepts could mean in some future Reality, which is upon us to decide on Now. (author)

Science or Fiction - Is there a Future for Nuclear

Energy Technology Data Exchange (ETDEWEB)

Wenisch, A.; Kromp, R.; Reinberger, D.

2007-07-01

This booklet served as preparation for both participants and speakers at the conference »Science or Fiction – Is there a Future for Nuclear?«. This international conference on fusion energy and new nuclear reactor models was organized by Global 2000/Friends of the Earth Austria and took place 8 November 2007 in Vienna. This booklet contains our contribution to the ongoing discussion about future energy security and what paths we should take. We focus on the possible future scenarios for nuclear power. The nuclear industry is trying to secure its own future by reintroducing old concepts like nuclear fusion and updating old fission reactors in so-called Generation IV systems. While there is enough information available on both fission and fusion energy from project financiers, research institutions and the European Commission, who gave the lion share of energy research funds into fusion research, we attempt here to provide a broader perspective and examine how much is Fiction and what these concepts could mean in some future Reality, which is upon us to decide on Now. (author)

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.)

Fusion reactor design: On the road to commercialization

International Nuclear Information System (INIS)

Kulcinski, G.L.

1984-01-01

The worldwide effort in fusion is now approximately 2 billion dollars per year and over 12 billion dollars has been invested since 1951 in developing this energy source for the 21st century. A vital component of the past efforts in fusion research has been the conceptual design activities performed by scientists and engineers around the world. Almost 80 such major designs of Tokamak, Mirror, Laser and Ion Beam Reactors have been published and this article discusses how recent conceptual designs have afftected our perception of future fusion reactor performance. (orig.) [de

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...

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)

Centralized supercomputer support for magnetic fusion energy research

International Nuclear Information System (INIS)

Fuss, D.; Tull, G.G.

1984-01-01

High-speed computers with large memories are vital to magnetic fusion energy research. Magnetohydrodynamic (MHD), transport, equilibrium, Vlasov, particle, and Fokker-Planck codes that model plasma behavior play an important role in designing experimental hardware and interpreting the resulting data, as well as in advancing plasma theory itself. The size, architecture, and software of supercomputers to run these codes are often the crucial constraints on the benefits such computational modeling can provide. Hence, vector computers such as the CRAY-1 offer a valuable research resource. To meet the computational needs of the fusion program, the National Magnetic Fusion Energy Computer Center (NMFECC) was established in 1974 at the Lawrence Livermore National Laboratory. Supercomputers at the central computing facility are linked to smaller computer centers at each of the major fusion laboratories by a satellite communication network. In addition to providing large-scale computing, the NMFECC environment stimulates collaboration and the sharing of computer codes and data among the many fusion researchers in a cost-effective manner

Closed loop control of the sawtooth instability in nuclear fusion

NARCIS (Netherlands)

Witvoet, G.; Steinbuch, M.; Westerhof, E.; Doelman, N.J.; Baar, de M.R.

2010-01-01

In nuclear fusion the sawtooth instability is an important plasma phenomenon, having both positive and negative effects on the tokamak plasma. Control of its period is essential in future nuclear fusion reactors. This paper presents a control oriented model of the sawtooth instability, with current

Future development of large steam turbines

International Nuclear Information System (INIS)

Chevance, A.

1975-01-01

An attempt is made to forecast the future of the large steam turbines till 1985. Three parameters affect the development of large turbines: 1) unit output; and a 2000 to 2500MW output may be scheduled; 2) steam quality: and two steam qualities may be considered: medium pressure saturated or slightly overheated steam (light water, heavy water); light enthalpie drop, high pressure steam, high temperature; high enthalpic drop; and 3) the quality of cooling supply. The largest range to be considered might be: open system cooling for sea-sites; humid tower cooling and dry tower cooling. Bi-fluid cooling cycles should be also mentioned. From the study of these influencing factors, it appears that the constructor, for an output of about 2500MW should have at his disposal the followings: two construction technologies for inlet parts and for high and intermediate pressure parts corresponding to both steam qualities; exhaust sections suitable for the different qualities of cooling supply. The two construction technologies with the two steam qualities already exist and involve no major developments. But, the exhaust section sets the question of rotational speed [fr

Real-time control of fusion reactors

International Nuclear Information System (INIS)

Goncalves, B.; Sousa, J.; Varandas, C.A.F.

2010-01-01

The next generation fusion experiments, e.g. ITER, will be highly complex and raise new challenges in the field of control and data acquisition systems. The more advanced operation scenarios have to be capable of sustaining long pulse steady-state plasma and to suppress plasma instabilities almost completely. Such scenarios will heavily rely on Multiple-Input-Multiple-Output (MIMO) fast control systems. To ensure safety for the operation these systems have to be robust and resilient to faults while ensuring high availability. Mindful of the importance of such features for future fusion experiments ATCA based systems have been successfully used in fusion experiment as MIMO fast controller. This is the most promising architecture to substantially enhance the performance and capability of existing standard systems delivering well high throughput as well as high availability. The real-time control needs of a fusion experiment, the rational for the presently pursued solutions, the existing problems and the broad scientific and technical questions that need to be addressed on the path to a fusion power plant will be discussed.

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

Induction linac drivers for commercial heavy-ion beam fusion

International Nuclear Information System (INIS)

Keefe, D.

1987-11-01

This paper discusses induction linac drivers necessary to accelerate heavy ions at inertial fusion targets. Topics discussed are: driver configurations, the current-amplifying induction linac, high current beam behavior and emittance growth, new considerations for driver design, the heavy ion fusion systems study, and future studies. 13 refs., 6 figs., 1 tab

Utility requirements for fusion power

International Nuclear Information System (INIS)

DeBellis, R.J.

1977-03-01

A four-man-month study, jointly funded by EPRI and McDonnell Douglas Astronautics Company-EAST, was undertaken to identify the utility requirements of fusion power and define a role for the utilities in the fusion development process during the 1980's. This report, preliminary in nature, serves mainly as a planning document for future requirements analyses. A requirements organization was defined to consist of three major chronological phases: research and development, plant installation, and plant operation. Thirty-seven requirements were identified, covering all categories. In addition, training, environment, safety, licensing, and utility model were identified as five matrix-type requirements. As the requirement definition process continued during the study period, comments received from utility representatives revealed a consistency of key issues in the fusion development process. These issues form the basis for the eventual establishment of definitive roles for the utilities during the 1980's. The issues are not meant to reflect a negative view of fusion, but are items which must be solved before fusion can be introduced commercially as an electrical power source. As a result of this requirements study, preliminary candidate roles for the utilities in the fusion development process during the 1980's were identified as public education, commercialization studies, industry investment analyses, training plan implementation, alternate reactor concept development, ERDA concept design review, and requirements refinement

Fusion instrumentation and control: a development strategy

International Nuclear Information System (INIS)

Hsu, P.Y.; Greninger, R.C.; Longhurst, G.R.; Madden, P.

1981-01-01

We have examined requirements for a fusion instrumentation and control development program to determine where emphasis is needed. The complex, fast, and closely coupled system dynamics of fusion reactors reveal a need for a rigorous approach to the development of instrumentation and control systems. A framework for such a development program should concentrate on three principal need areas: the operator-machine interface, the data and control system architecture, and fusion compatible instruments and sensors. System dynamics characterization of the whole fusion reactor system is also needed to facilitate the implementation process in each of these areas. Finally, the future need to make the instrumentation and control system compatible with the requirements of a commercial plant is met by applying transition technology. These needs form the basis for the program tasks suggested

Lipid Acrobatics in the Membrane Fusion Arena

NARCIS (Netherlands)

Markvoort, Albert J.; Marrink, Siewert J.; Chernomordik, Leonid V.; Kozlov, Michael M.

2011-01-01

In this review, we describe the recent contribution of computer simulation approaches to unravel the molecular details of membrane fusion. Over the past decade, fusion between apposed membranes and vesicles has been studied using a large variety of simulation methods and systems. Despite the variety

Electric vehicles to support large wind power penetration in future danish power systems

DEFF Research Database (Denmark)

Pillai, Jayakrishnan Radhakrishna; Bak-Jensen, Birgitte; Thøgersen, Paul

2012-01-01

Electric Vehicles (EVs) could play major role in the future intelligent grids to support a large penetration of renewable energy in Denmark, especially electricity production from wind turbines. The future power systems aims to phase-out big conventional fossil-fueled generators with large number...... on low voltage residential networks. Significant amount of EVs could be integrated in local distribution grids with the support of intelligent grid and smart charging strategies....

A schedule for fusion research development and international collaboration

International Nuclear Information System (INIS)

Kakihana, H.

1983-01-01

In order to reach their goal of commercial fusion power reactors, development must proceed in a series of basic stages. Each step is expected to incur an increased level of cost. The cost-sharing benefits of international collaboration will become increasingly important and attractive with each successive step preceding commercialization. Outstanding examples of implementation of international collaboration in fusion include the JET project and the INTOR workshop which lend encouragement for the prospects for international collaboration in fusion in the future. (author)

Ceramic sphere-pac breeder design for fusion blankets

International Nuclear Information System (INIS)

Gierszewski, P.J.; Sullivan, J.D.

1991-01-01

Randomly packed beds of ceramic spheres are a practical approach to surrounding fusion plasmas with tritium-breeding material. This paper examines the general properties of sphere-pac beds for application in fusion breeder blankets. The design considerations and models are reviewed for packing, tritium breeding and recovery, thermal conductivity, purge-gas pressure drop, mechanical behavior and fabrication. The design correlations are compared against available fusion ceramic data. Specific conclusions are that ternary (three-size) beds are not attractive for fusion blankets, and that the fusion spheres should be as large as possible subject primarily to packing constraints. (orig.)

A preliminary study of a D-T tokamak fusion reactor with advanced blanket using the compact fusion advanced Brayton (CFAB) cycle

International Nuclear Information System (INIS)

Yoshikawa, K.; Ishikawa, M.; Umoto, J.; Fukuyama, A.; Mitarai, O.; Okamoto, M.; Sekimoto, H.; Nagatsu, M.

1995-01-01

Preliminary key issues for a synchrotron radiation-enhanced compact fusion advanced Brayton (CFAB) cycle fusion reactor similar to the CFAR (compact fusion advanced Rankine) cycle reactor are presented. These include plasma operation windows as a function of the first wall reflectivity and related issues, to estimate an allowance for deterioration of the first wall reflectivity due to dpa effects. It was found theoretically that first wall reflectivities down to 0.8 are still adequate for operation at an energy confinement scaling of 3 times Kaye-Goldston. Measurements of the graphite first wall reflectivities at Nagoya University indicate excellent reflectivities in excess of 90% for CC-312, PCC-2S, and PD-330S in the submillimeter regime, even at high temperatures in excess of 1000K. Some engineering issues inherent to the CFAB cycle are also discussed briefly in comparison with the CFAR cycle which uses hazardous limited-resource materials but is capable of using mercury as coolant for high heat removal. The CFAB cycle using helium coolant is found to achieve higher net plant conversion efficiencies in excess 60% using a non-equilibrium magnetohydrodynamic disk generator in the moderate pressure range, even at the cost of a relatively large pumping power, and at the penalty of high temperature materials, although excellent heat removal characteristics in the moderate pressure range need to be guaranteed in the future. (orig.)

Future changes in large-scale transport and stratosphere-troposphere exchange

Science.gov (United States)

Abalos, M.; Randel, W. J.; Kinnison, D. E.; Garcia, R. R.

2017-12-01

Future changes in large-scale transport are investigated in long-term (1955-2099) simulations of the Community Earth System Model - Whole Atmosphere Community Climate Model (CESM-WACCM) under an RCP6.0 climate change scenario. We examine artificial passive tracers in order to isolate transport changes from future changes in emissions and chemical processes. The model suggests enhanced stratosphere-troposphere exchange in both directions (STE), with decreasing tropospheric and increasing stratospheric tracer concentrations in the troposphere. Changes in the different transport processes are evaluated using the Transformed Eulerian Mean continuity equation, including parameterized convective transport. Dynamical changes associated with the rise of the tropopause height are shown to play a crucial role on future transport trends.

FUSION technology programme 2003-2006

International Nuclear Information System (INIS)

Karttunen, S.; Rantamaeki, K.

2007-01-01

This report summarises the results of the FUSION technology programme during the period between 2003-2006. FUSION is a continuation of the previous FFusion and FFusion2 technology programmes that took place from 1993 to 2002. The FUSION technology programme was fully integrated into the European Fusion Programme in the sixth Framework Programme (Euratom), through the bilateral Contract of Association between Euratom and Tekes and the multilateral European Fusion Development Agreement (EFDA). The Association Euratom-Tekes was established in 1995. At the moment, there are 26 Euratom Fusion associations working together as an European Research Area. There are four research areas in the FUSION technology programme: (1) fusion physics and plasma engineering, (2) vessel/in-vessel materials, joints and components, (3) in-vessel remote handling systems, and (4) system studies. The FUSION team consists of research groups from the Technical Research Centre of Finland (VTT), the Helsinki, Tampere and Lappeenranta Universities of Technology and the University of Helsinki. The co-ordinating unit is VTT. A key element of the FUSION programme is the close collaboration between VTT, the universities and the industry, which has resulted in dynamic and sufficiently large research teams to tackle challenging research and development projects. The distribution of work between research institutes and industry has also been clear. Industrial activities related to the FUSION programme are co-ordinated through the 'Big Science' Project by Finpro and Prizztech. The total expenditure of the FUSION technology programme for 2003-2006 amounted to euro 14,9 million in research work at VTT and the universities with an additional euro 3,5 million for projects by the Finnish companies including the industry co-ordination. The funding of the FUSION programme and related industrial projects was mainly provided by Tekes (37%), Euratom (38%) and the participating institutes and industry (24%). The

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)

Magnetic fusion 1985: what next

International Nuclear Information System (INIS)

Fowler, T.K.

1985-03-01

Recent budget reductions for magnetic fusion have led to a re-examination of program schedules and objectives. Faced with delays and postponement of major facilities as previously planned, some have called for a near-term focus on science, others have stressed technology. This talk will suggest a different focus as the keynote for this conference, namely, the applications of fusion. There is no doubt that plasma science is by now mature and fusion technology is at the forefront. This has and will continue to benefit many fields of endeavor, both in actual new discoveries and techniques and in attracting and training scientists and engineers who move on to make significant contributions in science, defense and industry. Nonetheless, however superb the science or how challenging the technology, these are means, not ends. To maintain its support, the magnetic fusion program must also offer the promise of power reactors that could be competitive in the future. At this conference, several new reactor designs will be described that claim to be smaller and economically competitive with fission reactors while retaining the environmental and safety characteristics that are the hallmark of fusion. The American Nuclear Society is an appropriate forum in which to examine these new designs critically, and to stimulate better ideas and improvements. As a preview, this talk will include brief discussions of new tokamak, tandem mirror and reversed field pinch reactor designs to be presented in later sessions. Finally, as a preview of the session on fusion breeders, the talk will explore once again the economic implications of a new nuclear age, beginning with improved fission reactors fueled by fusion breeders, then ultimately evolving to reactors based solely on fusion

Virtual laboratory for fusion research in Japan

International Nuclear Information System (INIS)

Tsuda, K.; Nagayama, Y.; Yamamoto, T.; Horiuchi, R.; Ishiguro, S.; Takami, S.

2008-01-01

A virtual laboratory system for nuclear fusion research in Japan has been developed using SuperSINET, which is a super high-speed network operated by National Institute of Informatics. Sixteen sites including major Japanese universities, Japan Atomic Energy Agency and National Institute for Fusion Science (NIFS) are mutually connected to SuperSINET with the speed of 1 Gbps by the end of 2006 fiscal year. Collaboration categories in this virtual laboratory are as follows: the large helical device (LHD) remote participation; the remote use of supercomputer system; and the all Japan ST (Spherical Tokamak) research program. This virtual laboratory is a closed network system, and is connected to the Internet through the NIFS firewall in order to keep higher security. Collaborators in a remote station can control their diagnostic devices at LHD and analyze the LHD data as they were at the LHD control room. Researchers in a remote station can use the supercomputer of NIFS in the same environment as NIFS. In this paper, we will describe detail of technologies and the present status of the virtual laboratory. Furthermore, the items that should be developed in the near future are also described

Additional gleaning of fusion energy development

International Nuclear Information System (INIS)

Yamamoto, Kenzo; Koizumi, Koichi

2002-09-01

This report summarizes the major topics in the history of fusion energy development in Japan from its dawn to the tokamak fusion experimental reactor, ITER. The domestic circumstances and situation in foreign countries in those days, and the details of each decision and discussion, are described. Since my previous writing, 'Forty years for Nuclear Fusion Energy Development - Big Science in Japan (1997, ERC Press. Co. Ltd.)', was a book which briefly summarize a large quantity of documents on the history, there are many points, which require additional detail explanation. This time, I selected and extracted major topics in the fusion research history, and added additional descriptions and my comments so as to supplement my previous writing. (author)

Magnetic Fusion Advisory Committee report on recommended fusion program priorities and strategy

International Nuclear Information System (INIS)

1983-09-01

The Magnetic Fusion Advisory Committee recommends a new program strategy with the following principal features: (1) Initiation in FY86 of the Tokamak Fusion Core Experiment (TFCX), a moderate-cost tokamak reactor device (less than $1 B PACE) designed to achieve ignition and long-pulse equilibrium burn. Careful trade-off studies are needed before making key design choices in interrelated technology areas. Cost reductions relative to earlier plans can be realized by exploiting new plasma technology, by locating the TFCX at the TFTR site, and by assigning responsibility for complementary reactor engineering tasks to other sectors of the fusion program. (2) Potential utilization of the MFTF Upgrade to provide a cost-effective means for quasi-steady-state testing of blanket and power-system components, complementary to TFCX. This will depend on future assessments of the data base for tandem mirrors. (3) Vigorous pursuit of the broad US base program in magnetic confinement, including new machine starts, where appropriate, at approximately the present total level of support. (4) Utilization of Development and Technology programs in plasma and magnet technology in support of specific hardware requirements of the TFCX and of other major fusion facilities, so as to minimize overall program cost

Data fusion qualitative sensitivity analysis

International Nuclear Information System (INIS)

Clayton, E.A.; Lewis, R.E.

1995-09-01

Pacific Northwest Laboratory was tasked with testing, debugging, and refining the Hanford Site data fusion workstation (DFW), with the assistance of Coleman Research Corporation (CRC), before delivering the DFW to the environmental restoration client at the Hanford Site. Data fusion is the mathematical combination (or fusion) of disparate data sets into a single interpretation. The data fusion software used in this study was developed by CRC. The data fusion software developed by CRC was initially demonstrated on a data set collected at the Hanford Site where three types of data were combined. These data were (1) seismic reflection, (2) seismic refraction, and (3) depth to geologic horizons. The fused results included a contour map of the top of a low-permeability horizon. This report discusses the results of a sensitivity analysis of data fusion software to variations in its input parameters. The data fusion software developed by CRC has a large number of input parameters that can be varied by the user and that influence the results of data fusion. Many of these parameters are defined as part of the earth model. The earth model is a series of 3-dimensional polynomials with horizontal spatial coordinates as the independent variables and either subsurface layer depth or values of various properties within these layers (e.g., compression wave velocity, resistivity) as the dependent variables

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

Inertial fusion energy: A clearer view of the environmental and safety perspectives

International Nuclear Information System (INIS)

Latkowski, J.F.

1996-11-01

If fusion energy is to achieve its full potential for safety and environmental (S ampersand E) advantages, the S ampersand E characteristics of fusion power plant designs must be quantified and understood, and the resulting insights must be embodied in the ongoing process of development of fusion energy. As part of this task, the present work compares S ampersand E characteristics of five inertial and two magnetic fusion power plant designs. For each design, a set of radiological hazard indices has been calculated with a system of computer codes and data libraries assembled for this purpose. These indices quantify the radiological hazards associated with the operation of fusion power plants with respect to three classes of hazard: accidents, occupational exposure, and waste disposal. The three classes of hazard have been qualitatively integrated to rank the best and worst fusion power plant designs with respect to S ampersand E characteristics. From these rankings, the specific designs, and other S ampersand E trends, design features that result in S ampersand E advantages have been identified. Additionally, key areas for future fusion research have been identified. Specific experiments needed include the investigation of elemental release rates (expanded to include many more materials) and the verification of sequential charged-particle reactions. Improvements to the calculational methodology are recommended to enable future comparative analyses to represent more accurately the radiological hazards presented by fusion power plants. Finally, future work must consider economic effects. Trade-offs among design features will be decided not by S ampersand E characteristics alone, but also by cost-benefit analyses. 118 refs., 35 figs., 35 tabs

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

Nuclear Fusion Research Understanding Plasma-Surface Interactions

CERN Document Server

Clark, Robert E.H

2005-01-01

It became clear in the early days of fusion research that the effects of the containment vessel (erosion of "impurities") degrade the overall fusion plasma performance. Progress in controlled nuclear fusion research over the last decade has led to magnetically confined plasmas that, in turn, are sufficiently powerful to damage the vessel structures over its lifetime. This book reviews current understanding and concepts to deal with this remaining critical design issue for fusion reactors. It reviews both progress and open questions, largely in terms of available and sought-after plasma-surface interaction data and atomic/molecular data related to these "plasma edge" issues.

Fusion program research materials inventory

International Nuclear Information System (INIS)

Roche, T.K.; Wiffen, F.W.; Davis, J.W.; Lechtenberg, T.A.

1984-01-01

Oak Ridge National Laboratory maintains a central inventory of research materials to provide a common supply of materials for the Fusion Reactor Materials Program. This will minimize unintended material variations and provide for economy in procurement and for centralized record keeping. Initially this inventory is to focus on materials related to first-wall and structural applications and related research, but various special purpose materials may be added in the future. The use of materials from this inventory for research that is coordinated with or otherwise related technically to the Fusion Reactor Materials Program of DOE is encouraged

Laser fusion experiments at LLL

Energy Technology Data Exchange (ETDEWEB)

Ahlstrom, H.G.

1980-06-16

These notes present the experimental basis and status for laser fusion as developed at LLL. Two other chapters, one authored by K.A. Brueckner and the other by C. Max, present the theoretical implosion physics and laser plasma interaction physics. The notes consist of six sections. The first is an introductory section which provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future.

Laser fusion experiments at LLL

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1980-01-01

These notes present the experimental basis and status for laser fusion as developed at LLL. Two other chapters, one authored by K.A. Brueckner and the other by C. Max, present the theoretical implosion physics and laser plasma interaction physics. The notes consist of six sections. The first is an introductory section which provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future

Initiative taken by India in magnetically confined fusion reactor

International Nuclear Information System (INIS)

Bora, Dhiraj

2017-01-01

There is a growing gap between demand and supply of energy in the world. Any attempt to develop new and cleaner sources of energy to meet the future global requirement is welcome. Therefore, it is attractive to think of having fusion as an alternate clean source of energy to contribute in the energy mix towards the second half of the century, with a virtually inexhaustible fuel supply. The environmental impact of fusion would be acceptable and relatively safe. These advantages have driven the world fusion research programme since its inception. Indian progress in fusion science and technology and participation in ITER will be discussed during the talk

Evaluation of economical introduction of nuclear fusion based on a long-term world energy and environment model

International Nuclear Information System (INIS)

Tokimatsu, K.; Asaoka, Y.; Okano, K.; Konishi, S.; Ogawa, Y.; Yamaji, K.

2003-01-01

Debates about whether or not to invest heavily in nuclear fusion as a future innovative energy option have been made within the context of energy technology development strategies. The time frame by which nuclear fusion could become competitive in the energy market has not been adequately studied, nor has roles of the nuclear fusion in energy systems and the environment. The present study has two objectives. One is to reveal the conditions under which nuclear fusion could be introduced economically (hereafter, we refer to such introductory conditions as breakeven prices) in future energy systems. The other objective is to evaluate the future roles of nuclear fusion in energy systems and in the environment. Here we chose two roles that nuclear fusion will take on when breakeven prices are achieved: i) reduction of annual global total energy systems cost, and ii) mitigation of carbon tax (shadow price of carbon) under CO 2 constraints. Future uncertainties are key issues in evaluating nuclear fusion. Here we treated the following uncertainties: energy demand scenarios, introduction time frame for nuclear fusion, capacity projections of nuclear fusion, CO 2 target in 2100. From our investigations, we conclude that the presently designed nuclear fusion reactors may be ready for economical introduction into energy systems beginning around 2050-2060, and we can confirm that the favorable introduction of the reactors would reduce both the annual energy systems cost and the carbon tax (the shadow price of carbon) under a CO 2 concentration constraint; however, latter introduction of them decreases the cost and the tax less than five times. Earlier introduction of nuclear fusion reactors are desirable for energy systems and environment. (author)

Fusion - the programme in the UK - and other thoughts

International Nuclear Information System (INIS)

Carruthers, R

1978-01-01

The Fusion Programme in the Euratom--UKAEA Fusion Association is mainly one of plasma confinement studies in four major experimental areas. Conceptual studies of fusion reactors have been based upon the tokamak and the reversed field pinch. Particular attention has been given to the potential operating problems of toroidal fusion reactors in order to establish design principles which take note of the high availability essential in a power plant. Future plans for fusion power programmes are discussed and it is suggested that they are not obviously the quickest or most cost effective ways to establishing the credibility of fusion. It is proposed that a more aggressive programme which involved taking calculated risks could be quicker and cheaper. An additional, important advantage would be to attract into the fusion programme good engineers who feel the need to be motivated by action on a time scale less than the 30 to 50 years of much present planning

Irradiation damage of ferritic/martensitic steels: Fusion program data applied to a spallation neutron source

International Nuclear Information System (INIS)

Klueh, R.L.

1997-01-01

Ferritic/martensitic steels were chosen as candidates for future fusion power plants because of their superior swelling resistance and better thermal properties than austenitic stainless steels. For the same reasons, these steels are being considered for the target structure of a spallation neutron source, where the structural materials will experience even more extreme irradiation conditions than expected in a fusion power plant first wall (i.e., high-energy neutrons that produce large amounts of displacement damage and transmutation helium). Extensive studies on the effects of neutron irradiation on the mechanical properties of ferritic/martensitic steels indicate that the major problem involves the effect of irradiation on fracture, as determined by a Charpy impact test. There are indications that helium can affect the impact behavior. Even more helium will be produced in a spallation neutron target material than in the first wall of a fusion power plant, making helium effects a prime concern for both applications. 39 refs., 10 figs

The need for fusion

International Nuclear Information System (INIS)

Llewellyn Smith, Chris

2005-01-01

World energy use is predicted to double in the next 40 years. Currently 80% is provided by burning fossil fuels, but this is not sustainable indefinitely because (i) it is driving climate change, and (ii) fossil fuels will eventually be exhausted (starting with oil). The resulting potential energy crisis requires increased investment in energy research and development (which is currently very small on the scale of the $3 trillion p.a. energy market, and falling). The wide portfolio of energy work that should be supported must include fusion, which is one of the very few options that are capable in principle of supplying a large fraction of need. The case for fusion has been strengthened by recent advances in plasma physics and fusion technology that are reflected in the forthcoming European Fusion Power Plant Conceptual Study, which addresses safety and cost issues. The big questions are - How can we deliver fusion power as fast as possible? How long is it likely to take? I argue for a fast track programme, and describe a fast-track model developed at Culham, which is intended to stimulate debate on the way ahead and the resources that are needed

Fusion programme 1976-1980

International Nuclear Information System (INIS)

Bock, R.; Wollenberger, H.; Kaufmann, M.; Wolf, G.H.; Heinz, W.

1981-01-01

In 1980, the Gesellschaft fuer Schwerionenforschung (GSI) in Darmstadt, the fifth large-scale research institution to join the agreement for co-operation in the fusion-centered plasmaphysics and fusion reactor technology made between the HMI, the IPP, the KFA and the KfK in 1974. Under the project responsibility of the GSI the BMFT have investigated whether the inertial confinement with heavy ion beams can be used as an alternative pathway to the fusion reactor in the Federal Republic of Germany. As in the past years, the co-operation with universities has been maintained, where especially basic research in plasma physics has been promoted in projects financed by the centers on the one hand, and by means of the main point 'fusion-centered plasma physics' set up by the Deutsche Forschungsgemeinschaft on the other hand. The topics of these activities are listed. The summary given in this brief report singles out only a few important results of the work on magnetic plasma confinement, fusion technology and inertial confinement. This information is to be completed and depend by studying the scientific reports or individual publications of the centers. The addresses where to request these reports are listed. (orig.) [de

Large superconductors and joints for fusion magnets: From conceptual design to testing at full scale

Science.gov (United States)

Ciazynski, D.; Duchateau, J. L.; Decool, P.; Libeyre, P.; Turck, B.

2001-02-01

A new kind of superconductor, using the cable-in-conduit concept, is emerging, mainly in the context of fusion activity. At present no large Nb3Sn magnet in the world is operating using this concept. The difficulty of this technology, which has now been studied for 20 years, is that it requires major advances in several interconnected new fields, such as handling a large number (1000) of superconducting strands, high current conductors (50 kA), forced flow cryogenics, Nb3Sn technology, low loss conductors in pulsed operation, high current connections and high voltage insulation (10 kV), as well as demonstration of its economical and industrial feasibility. CEA has been very much involved, during the past ten years, in this development, which took place in the framework of the NET and ITER technological programmes. One major milestone was reached in 1998-1999 with the successful tests by Euratom-CEA of three full size conductor and connection samples in the SULTAN facility in Switzerland.

Economic potential of magnetic fusion energy

International Nuclear Information System (INIS)

Henning, C.D.

1981-01-01

Scientific feasibility of magnetic fusion is no longer seriously in doubt. Rapid advances have been made in both tokamak and mirror research, leading to a demonstration in the TFTR tokamak at Princeton in 1982 and the tandem mirror MFTF-B at Livermore in 1985. Accordingly, the basis is established for an aggressive engineering thrust to develop a reactor within this century. However, care must be taken to guide the fusion program towards an economically and environmentally viable goal. While the fusion fuels are essentially free, capital costs of reactors appear to be at least as large as current power plants. Accordingly, the price of electricity will not decline, and capital availability for reactor constructions will be important. Details of reactor cost projections are discussed and mechanisms suggested for fusion power implementation. Also discussed are some environmental and safety aspects of magnetic fusion

TMX: a new fusion plasma experiment

International Nuclear Information System (INIS)

Anon.

1977-01-01

The primary goal of the magnetic fusion energy program at LLL is the development of a technically and economically feasible approach to the generation of fusion energy. Results from our earlier 2XIIB experiment lead us to believe that a fusion power plant based on a mirror system is technically feasible, assuming a favorable extrapolation to plasmas of reactor size. Achieving economic feasibility is more difficult. For power-producing applications, a reactor needs a large Q, the ratio of fusion power output to the power injected to sustain the system. In a conventional mirror reactor, the fusion power is only about equal to the power injected by the neutral beams--that is, Q is only about unity. A new idea, the tandem mirror concept described in this article, promises to increase this gain, enhancing Q by at least a factor of 5

Radar image and data fusion for natural hazards characterisation

Science.gov (United States)

Lu, Zhong; Dzurisin, Daniel; Jung, Hyung-Sup; Zhang, Jixian; Zhang, Yonghong

2010-01-01

Fusion of synthetic aperture radar (SAR) images through interferometric, polarimetric and tomographic processing provides an all - weather imaging capability to characterise and monitor various natural hazards. This article outlines interferometric synthetic aperture radar (InSAR) processing and products and their utility for natural hazards characterisation, provides an overview of the techniques and applications related to fusion of SAR/InSAR images with optical and other images and highlights the emerging SAR fusion technologies. In addition to providing precise land - surface digital elevation maps, SAR - derived imaging products can map millimetre - scale elevation changes driven by volcanic, seismic and hydrogeologic processes, by landslides and wildfires and other natural hazards. With products derived from the fusion of SAR and other images, scientists can monitor the progress of flooding, estimate water storage changes in wetlands for improved hydrological modelling predictions and assessments of future flood impacts and map vegetation structure on a global scale and monitor its changes due to such processes as fire, volcanic eruption and deforestation. With the availability of SAR images in near real - time from multiple satellites in the near future, the fusion of SAR images with other images and data is playing an increasingly important role in understanding and forecasting natural hazards.

History of controlled nuclear fusion in Japan

International Nuclear Information System (INIS)

Uematsu, Eisui; Nishio, Shigeko; Takeda, Tatsuoki

2001-01-01

A research development of nuclear fusion was divided four periods: the first period as prehistory (until about 1955), the second period as begin of research (1955 to 1969), the third as the growth period (1970 to 1985) and the forth as the large tokamak age. In this paper I explained the second period, because general physicists and young plasma and controlled nuclear fusion researcher did not know about this period. The controlled nuclear fusion research was begun by the experiment of hydrogen bomb by USA and USSR in 1952 and 1953. In Japan, on the basis of many societies, 'The Controlled Nuclear Fusion Meeting' was established as an independent system and KAKEA (Journal of Fusion Research) was published in 1958. Japan government began to make the system by the Nuclear Commission in 1957. The main research devices in 1962 were linear pinch, mirror device, toroidal pinch, helical system, plasma gun and plasma measurement. USSR showed the excellent results of tokamak device in 1968. Ookawa spoke the effect of the average minimum-B, the best report in this period, at the second IAEA meeting, 1965. JAERI constructed JFT-1 and JFT-2, the latter was the first class device in the world and made the first step of Japanese research into the world, for examples, to attain the equilibrium of divertor plasma and to control impurity. Many research centers of controlled fusion were established in many universities in Japan from 1966 to 1980. Cooperation researchs between Japan and USA, USSR and many countries has been carried out after 1978: JIFT (Joint Institute for Fusion Theory) and FPPC (Fusion Power Coordinating Committee). The important results increased in this period. After 1985, the research activities are processing and data increased very fast depend on the larger devices and system, good measurement system and development of information system. JT-60 in JAERI opened to the large tokamak period. It led controlled fusion researchs in the world the same as TFTR (US

Nuclear-fusion research. To bring the sun on the earh

International Nuclear Information System (INIS)

Zohm, Hartmut

2009-01-01

The course treats first the foundations of nuclear fusion. In the second part the concepts for the realization of nuclear fusion in the laboratory are described. Finally in the last part a survey on the present status of the research as well an outlook on future work is given

On stimulated scattering of laser light in inertial fusion energy targets

International Nuclear Information System (INIS)

Nikolic, Lj; Skoric, M.M.; Ishiguro, S.; Sato, T.

2002-11-01

Propagation of a laser light through regions of an underdense plasma is an active research topic in laser fusion. In particular, a large effort has been invested in studies of stimulated Raman scattering (SRS) and stimulated Brillouin scattering (SBS) which can reflect laser energy and produce energetic particles to preheat a fusion energy target. Experiments, theory and simulations agree on a complex interplay between various laser-plasma instabilities. By particle-in-cell simulations of an underdense electron-plasma, we have found, apart from the standard SRS, a strong backscattering near the electron plasma frequency at densities beyond the quarter critical. This novel instability, recognized in recent experiments as stimulated laser scattering on a trapped electron-acoustic mode (SEAS), is absent from a classical theory of laser-parametric instabilities. A parametric excitation of SEAS instability, is explained by a three-wave resonant decay of the incident laser light into a standing backscattered wave and a slow trapped electron acoustic wave (ω p ). Large SEAS pulsations, eventually suppressed by relativistic heating of electrons, are observed in our simulations. This phenomenon seems relevant to future hohlraum target and fast ignition experiments. (author)

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

Safety and environmental aspects of fusion reactors

International Nuclear Information System (INIS)

Kilic, H.; Jensen, B.

1982-01-01

This paper deals with those problems concerning safety and environmental aspects of the future fusion reactors (e.g. fuel cycle, magnetic failure, after heat disturbances, radioactive waste and magnetic field)

Historic overview of inertial confinement fusion: What have we learned

International Nuclear Information System (INIS)

Glass, A.J.

1986-01-01

Although laser fusion has been the subject of research since the early 1960s, it has only been intensively studied for about 14 years. During that time, substantive advances have been made in our understanding of the complex physics of laser-heated plasmas, in the development of sophisticated diagnostic instrumentation, and in the technology of fusion targets and inertial fusion drivers. These advances will be reviewed. Of equal importance are the lessons learned in the economic and political arenas. These lessons may be of greater significance for scientific endeavors in other fields of research. The economic and political issues surrounding inertial fusion research will be discussed. Possible future directions for inertial fusion development will be presented

Hyperenhanced Li - Li Chemonuclear Fusion

International Nuclear Information System (INIS)

Ikegami, Hidetsugu

2006-01-01

A new fusion scheme, the Li - Li chemonuclear fusion is presented, where nuclear fusion reactions are linked to atomic fusion reactions. Lithium ions are implanted on a surface of metallic Li liquid at an energy of nuclear stopping (several keV/amu). The ions collide slowly with liquid Li atoms without electronic excitation and lead to the Li - Li chemonuclear fusion through the formation of united atoms or quasi-C atoms at their turning points. Inside the quasi-atoms twin nuclei are confined within respective sub-pm scale spheres of zero-point oscillation and form themselves into ultradense intermediate nuclear complexes. Their density is million times as large as the solar interior density and close to densities of white dwarfs or white-dwarf progenitors of supernovae. This confinement of nuclear complexes is enormously prolonged towards the pycno-nuclear reactions induced by the zero-point oscillation under the presence of thermodynamic force specified by the Gibbs energy change in the quasi-atom formation in the liquid. Resulted rate enhancement of nuclear fusion by a factor of 10 48 has been anticipated. The enhancement is also argued in connection with the Bose-Einstein condensation

Remote maintenance of future fusion reactors - a challenge for rad-hard components and smart control strategies

International Nuclear Information System (INIS)

Decreton, M.; Geeter, J. De

1996-01-01

The future fusion reactor will need frequent maintenance turns, involving inspection, repair and parts replacement inside the vacuum vessel. These operations will require high payload manipulations in constrained space under very high gamma-radiation dose-rates and temperature. Present research is being undertaken to qualify the components of the handling machine under representative conditions, in the framework of the ITER international consortium. Simultaneously, challenging control strategies will be needed to achieve reliable tasking under very poor viewing conditions and elementary sensing help. The paper reviews the present state of the art on both issues and present results of the ongoing research themes among the partners of the ITER programme. In particular, SCK''centre-dot''CEN coordinates the ITER T252 task on Radiation Tolerance Assessment of Remote Handling Components. (UK)

A compensatory mutation provides resistance to disparate HIV fusion inhibitor peptides and enhances membrane fusion.

Directory of Open Access Journals (Sweden)

Matthew P Wood

Full Text Available Fusion inhibitors are a class of antiretroviral drugs used to prevent entry of HIV into host cells. Many of the fusion inhibitors being developed, including the drug enfuvirtide, are peptides designed to competitively inhibit the viral fusion protein gp41. With the emergence of drug resistance, there is an increased need for effective and unique alternatives within this class of antivirals. One such alternative is a class of cyclic, cationic, antimicrobial peptides known as θ-defensins, which are produced by many non-human primates and exhibit broad-spectrum antiviral and antibacterial activity. Currently, the θ-defensin analog RC-101 is being developed as a microbicide due to its specific antiviral activity, lack of toxicity to cells and tissues, and safety in animals. Understanding potential RC-101 resistance, and how resistance to other fusion inhibitors affects RC-101 susceptibility, is critical for future development. In previous studies, we identified a mutant, R5-tropic virus that had evolved partial resistance to RC-101 during in vitro selection. Here, we report that a secondary mutation in gp41 was found to restore replicative fitness, membrane fusion, and the rate of viral entry, which were compromised by an initial mutation providing partial RC-101 resistance. Interestingly, we show that RC-101 is effective against two enfuvirtide-resistant mutants, demonstrating the clinical importance of RC-101 as a unique fusion inhibitor. These findings both expand our understanding of HIV drug-resistance to diverse peptide fusion inhibitors and emphasize the significance of compensatory gp41 mutations.