Superconducting magnet and conductor research activities in the US fusion program

International Nuclear Information System (INIS)

Michael, P.C.; Schultz, J.H.; Antaya, T.A.; Ballinger, R.; Chiesa, L.; Feng, J.; Gung, C.-Y.; Harris, D.; Kim, J.-H.; Lee, P.; Martovetsky, N.; Minervini, J.V.; Radovinsky, A.; Salvetti, M.; Takayasu, M.; Titus, P.

2006-01-01

Fusion research in the United States is sponsored by the Department of Energy's Office of Fusion Energy Sciences (OFES). The OFES sponsors a wide range of programs to advance fusion science, fusion technology, and basic plasma science. Most experimental devices in the US fusion program are constructed using conventional technologies; however, a small portion of the fusion research program is directed towards large scale commercial power generation, which typically relies on superconductor technology to facilitate steady-state operation with high fusion power gain, Q. The superconductor portion of the US fusion research program is limited to a small number of laboratories including the Plasma Science and Fusion Center at MIT, Lawrence Livermore National Laboratory (LLNL), and the Applied Superconductivity Center at University of Wisconsin, Madison. Although Brookhaven National Laboratory (BNL) and Lawrence Berkeley National Laboratory (LBNL) are primarily sponsored by the US's High Energy Physics program, both have made significant contributions to advance the superconductor technology needed for the US fusion program. This paper summarizes recent superconductor activities in the US fusion program

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

Review of fusion research program: historical summary and program projections

Energy Technology Data Exchange (ETDEWEB)

Murphy, E.S.

1976-09-01

This report provides a brief review of the history and current status of fusion research in the United States. It also describes the Federally funded program aimed at the development of fusion reactors for electric power generation.

Sandia's Particle Beam Fusion Program

International Nuclear Information System (INIS)

Sweeney, M.A.

1979-01-01

Sandia's Particle Beam Fusion Program is investigating pulsed electron and light ion beam accelerators, with the goal of demonstrating the practical application of such drivers as igniters in inertial confinement fusion (ICF) reactors. Recent developments in the program are described. Traditionally, two requirements of ICF reactor operation have been the most difficult to satisfy in conceptual designs. Adequate standoff of critical components from damaging pellet emissions must be assured, and the shot repetition rate must be consistent with the desired reactor power level at reasonable pellet gains. Progress in power compression, beam focusing and transport, first-wall protection schemes, and net-energy-gain target design shows how these requirements can be met

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)

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

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

Technological implications of fusion power: requirements and status

International Nuclear Information System (INIS)

Steiner, D.

1978-01-01

The major technological requirements for fusion power, as implied by current conceptual designs of fusion power plants, are identified and assessed relative to the goals of existing technology programs. The focus of the discussion is on the tokamak magnetic confinement concept; however, key technological requirements of mirror magnetic confinement systems and of inertial confinement concepts will also be addressed. The required technology is examined on the basis of three general areas of concern: (a) the power balance, that is, the unique power handling requirements associated with the production of electrical power by fusion; (b) reactor design, focusing primarily on the requirements imposed by a tritium-based fuel cycle, thermal hydraulic considerations, and magnet systems; and (c) materials considerations, including radiation damage effects, neutron-induced activation, and resource limitations

Historical Perspective on the United States Fusion Program

International Nuclear Information System (INIS)

Dean, Stephen O.

2005-01-01

Progress and Policy is traced over the approximately 55 year history of the U. S. Fusion Program. The classified beginnings of the effort in the 1950s ended with declassification in 1958. The effort struggled during the 1960s, but ended on a positive note with the emergence of the tokamak and the promise of laser fusion. The decade of the 1970s was the 'Golden Age' of fusion, with large budget increases and the construction of many new facilities, including the Tokamak Fusion Test Reactor (TFTR) and the Shiva laser. The decade ended on a high note with the passage of the Magnetic Fusion Energy Engineering Act of 1980, overwhelming approved by Congress and signed by President Carter. The Act called for a '$20 billion, 20 year' effort aimed at construction of a fusion Demonstration Power Plant around the end of the century. The U. S. Magnetic Fusion Energy program has been on a downhill slide since 1980, both in terms of budgets and the construction of new facilities. The Inertial Confinement Fusion program, funded by Department of Energy Defense Programs, has faired considerably better, with the construction of many new facilities, including the National Ignition Facility (NIF)

New heavy-ion-fusion accelerator research program

International Nuclear Information System (INIS)

Herrmannsfeldt, W.B.

1983-05-01

This paper will briefly summarize the concepts of Heavy Ion Fusion (HIF), especially those aspects that are important to its potential for generating electrical power. It will also note highlights of the various HIF programs throughout the world. Especially significant is that the US Department of Energy (DOE) plans a program, beginning in 1984, aimed at determining the feasibility of using heavy ion accelerators as drivers for Inertial Confinement Fusion (ICF). The new program concentrates on the aspects of accelerator design that are important to ICF, and for this reason is called HIF Accelerator Research

STAR Power, an Interactive Educational Fusion CD with a Dynamic, Shaped Tokamak Power Plant Simulator

Science.gov (United States)

Leuer, J. A.; Lee, R. L.; Kellman, A. G.; Chapman Nutt, G. C., Jr.; Holley, G.; Larsen, T. A.

2000-10-01

We describe an interactive, educational fusion adventure game developed within our fusion education program. The theme of the adventure is start-up of a state-of-the-art fusion power plant. To gain access to the power plant control room, the student must complete several education modules, including topics on building an atom, fusion reactions, charged particle motion in electric and magnetic fields, and building a power plant. Review questions, a fusion video, library material and glossary provide additional resources. In the control room the student must start-up a complex, dynamic fusion power plant. The simulation model contains primary elements of a tokamak based device, including a magnetic shaper capable of producing limited and diverted elongated plasmas. A zero dimensional plasma model based on ITER scaling and containing rate based conservation equations provides dynamic feedback through major control parameters such as toroidal field, fueling rate and heating. The game is available for use on PC and Mac. computers. Copies will be available at the conference.

Pulsed power systems for inertial confinement fusion

International Nuclear Information System (INIS)

VanDevender, J.P.

1979-01-01

Sandis's Particle Beam Fusion Program is investigating pulsed electron and light ion beam accelerators with the goal of demonstrating the practical application of such drivers as igniters in inertial confinement fusion (ICF) reactors. The power and energy requirements for net energy gain are 10 14 to 10 15 W and 1 to 10 MJ. Recent advances in pulsed power and power flow technologies permit suitable accelerators to be built. The first accelerator of this new generation is PBFA I. It operates at 2 MV, 15 MA, 30 TW for 35 ns and is scheduled for completion in June 1980. The principles of this new accelerator technology and their application to ICF will be presented

Fusion power: massive research program aims at formidable problems, almost limitless potential

International Nuclear Information System (INIS)

Dingee, D.A.

1979-01-01

This article surveys extensively fusion development under the following topics: US research directions; inertial confinement fusion; foreign fusion efforts; fusion issues; fusion applications; and arguments for fusion development. Dr. Dingee points out that, despite persuasive arguments for development, fusion has as yet attracted no substantial constituency; and that winning greater support for fusion may thus require a considerable technical breakthrough (namely, proof of scientific feasibility or achievement of energy breakeven) - or a new focus on an energy source such as hybrids, which offer a nearer-term payoff than pure fusion. Dr. Dingee says the next major facility for magnetic confinement research (to be built in late 1980s) has not yet been selected, but will probably be an engineering test facility; there are similar plans for inertial confinement. Whichever type is chosen, the first experimental power reactor is scheduled for the first few years of the 2000's, this to be followed by commercial demonstration of fusion power in the 2010 to 2020 time frame. He points out, finally, that the complex technical and institutional issues are being considered in a climate in which the benefits of nuclear energy itself are being questioned; and that there is little doubt that future development is tied to overall decisions the nation will make regarding the value of nuclear energy

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.)

Strategic plan for the restructured US fusion energy sciences program

International Nuclear Information System (INIS)

1996-08-01

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

Nuclear fusion power

International Nuclear Information System (INIS)

Dinghee, D.A.

1983-01-01

In this chapter, fusion is compared with other inexhaustible energy sources. Research is currently being conducted both within and outside the USA. The current confinement principles of thermonuclear reactions are reveiwed with the discussion of economics mainly focusing on the magnetic confinement concepts. Environmental, health and safety factors are of great concern to the public and measures are being taken to address them. The magnetic fusion program logic and the inertial fusion program logic are compared

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

International Nuclear Information System (INIS)

Post, R.F.

1975-01-01

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

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

Structural materials challenges for fusion power systems

International Nuclear Information System (INIS)

Kurtz, Richard J.

2009-01-01

Full text: Structural materials in a fusion power system must function in an extraordinarily demanding environment that includes various combinations of high temperatures, reactive chemicals, time-dependent thermal and mechanical stresses, and intense damaging radiation. The fusion neutron environment produces displacement damage equivalent to displacing every atom in the material about 150 times during its expected service life, and changes in chemical composition by transmutation reactions, which includes creation of reactive and insoluble gases. Fundamental materials challenges that must be resolved to effectively harness fusion power include (1) understanding the relationships between material strength, ductility and resistance to cracking, (2) development of materials with extraordinary phase stability, high-temperature strength and resistance to radiation damage, (3) establishment of the means to control corrosion of materials exposed to aggressive environments, (4) development of technologies for large-scale fabrication and joining, and (5) design of structural materials that provide for an economically attractive fusion power system while simultaneously achieving safety and environmental acceptability goals. The most effective approach to solve these challenges is a science-based effort that couples development of physics-based, predictive models of materials behavior with key experiments to validate the models. The U.S. Fusion Materials Sciences program is engaged in an integrated effort of theory, modeling and experiments to develop structural materials that will enable fusion to reach its safety, environmental and economic competitiveness goals. In this presentation, an overview of recent progress on reduced activation ferritic/martensitic steels, nanocomposited ferritic alloys, and silicon carbide fiber reinforced composites for fusion applications will be given

Near and long term pulse power requirements for laser driven inertial confinement fusion

International Nuclear Information System (INIS)

Gagnon, W.L.

1979-01-01

At the Lawrence Livermore Laboraory, major emphasis has been placed upon the development of large, ND:glass laser systems in order to address the basic physics issues associated with light driven fusion targets. A parallel program is directed toward the development of lasers which exhibit higher efficiencies and shorter wavelengths and are thus more suitable as drivers for fusion power plants. This paper discusses the pulse power technology which has been developed to meet the near and far term needs of the laser fusion program at Livermore

Canada's Fusion Program

International Nuclear Information System (INIS)

Jackson, D. P.

1990-01-01

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

A thermonuclear fusion power program for Israel

International Nuclear Information System (INIS)

Friedman, Bruce

1985-01-01

Although lacking in financial and physical resources, Israel has a large base of scientific and technological talent that can be organized for the purpose of producing commercial fusion power reactors, thus allowing Israel to attain energy independence and acquiring a monetary inflow through royalties and reactor export. The limited partnership would be suitable for financing a significant portion of the project. Economic feasibility can be estimated through the use of one or more of the approaches supplied by the calculus of variations, cardinal utility theory, catastrophe theory, and noncooperative game theory. (author)

The German DEMO working group. Perspectives of a fusion power plant

International Nuclear Information System (INIS)

Hesch, Klaus

2013-01-01

Fusion development has many different challenges in the areas of plasma physics, fusion technologies, materials development and plasma wall interaction. For making fusion power a reality, a coherent approach is necessary, interlinking the different areas of work. To this end, the German fusion program started in 2010 the German DEMO Working Group, bringing together high-level experts from all the different fields, from the 3 German fusion centers Max-Planck-Institut fuer Plasmaphysik (IPP), Karlsruher Institut fuer Technologie (KIT) and Forschungszentrum Juelich (FZJ). An encompassing view of what will be needed with high priority, in plasma physics, in fusion technology and in the interrelation of the fields, to make fusion energy real, has been elaborated, and is presented here in a condensed way. On this basis, the 3 German fusion centers now are composing their work program, towards a fusion demonstration reactor DEMO. (orig.)

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)

LLL mirror fusion program: summary

International Nuclear Information System (INIS)

Fowler, T.K.

1977-01-01

During 1976, new Mirror Program plans have been laid out to take into account the significant advances during the last 18 months. The program is now focused on two new mirror concepts, field reversal and the tandem mirror, that can obtain high Q, defined as the ratio of fusion power output to the neutral-beam power injected to sustain the reaction. Theoretically, both concepts can attain Q = 5 or more, as compared to Q = 1 in previous mirror designs. Experimental planning for the next 5 years is complete in broad outline, and we are turning attention to what additional steps are necessary to reach our long-range goal of an experimental mirror reactor operating by 1990. Highlights of the events that have led to the above circumstance are listed, and experimental program plans are outlined

Personnel Safety for Future Magnetic Fusion Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee Cadwallader

2009-07-01

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

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

Configuration and layout of the tandem mirror Fusion Power Demonstrator

International Nuclear Information System (INIS)

Clarkson, I.R.; Neef, W.S.

1983-01-01

Studies have been performed during the past year to determine the configuration of a tandem mirror Fusion Power Demonstrator (FPD) machine capable of producing 1750 MW of fusion power. The FPD is seen as the next logical step after the Mirror Fusion Test Facility-B (MFTF-B) toward operation of a power reactor. The design of the FPD machine allows a phased construction: Phase I, a hydrogen or deuterium checkout machine; Phase 2, a DT breakeven machine; Phase 3, development of the Phase 2 machine to provide net power and act as a reactor demonstrator. These phases are essential to the development of remote handling equipment and the design of components that will ultimately be remotely handled. Phasing also permits more modes funding early in the program with some costs committed only after reaching major milestones

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-10-01

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

Magnetic Fusion Energy Program of India

International Nuclear Information System (INIS)

Sen, Abhijit

2013-01-01

The magnetic fusion energy program of India started in the early eighties with the construction of an indigenous tokamak device ADITYA at the Institute for Plasma Research in Gandhinagar. The initial thrust was on fundamental studies related to plasma instabilities and turbulence phenomena but there was also a significant emphasis on technology development in the areas of magnetics, high vacuum, radio-frequency heating and neutral beam technology. The program took a major leap forward in the late nineties with the decision to build a state-of-the-art superconducting tokamak (SST-1) that catapulted India into the mainstream of the international tokamak research effort. The SST experience and the associated technological and human resource development has now earned the country a place in the ITER collaboration as an equal partner with other major nations. Keeping in mind the rapidly growing and enormous energy needs of the future the program has also identified and launched key development projects that can lead us to a DEMO reactor and eventually a Fusion Power Plant in a systematic manner. I will give a brief overview of the early origins, the present status and some of the highlights of the future road map of the Indian Fusion Program. (author)

EDITORIAL: Safety aspects of fusion power plants

Science.gov (United States)

Kolbasov, B. N.

2007-07-01

importance for the fusion power plant research programmes. The objective of this Technical Meeting was to examine in an integrated way all the safety aspects anticipated to be relevant to the first fusion power plant prototype expected to become operational by the middle of the century, leading to the first generation of economically viable fusion power plants with attractive S&E features. After screening by guest editors and consideration by referees, 13 (out of 28) papers were accepted for publication. They are devoted to the following safety topics: power plant safety; fusion specific operational safety approaches; test blanket modules; accident analysis; tritium safety and inventories; decommissioning and waste. The paper `Main safety issues at the transition from ITER to fusion power plants' by W. Gulden et al (EU) highlights the differences between ITER and future fusion power plants with magnetic confinement (off-site dose acceptance criteria, consequences of accidents inside and outside the design basis, occupational radiation exposure, and waste management, including recycling and/or final disposal in repositories) on the basis of the most recent European fusion power plant conceptual study. Ongoing S&E studies within the US inertial fusion energy (IFE) community are focusing on two design concepts. These are the high average power laser (HAPL) programme for development of a dry-wall, laser-driven IFE power plant, and the Z-pinch IFE programme for the production of an economically-attractive power plant using high-yield Z-pinch-driven targets. The main safety issues related to these programmes are reviewed in the paper `Status of IFE safety and environmental activities in the US' by S. Reyes et al (USA). The authors propose future directions of research in the IFE S&E area. In the paper `Recent accomplishments and future directions in the US Fusion Safety & Environmental Program' D. Petti et al (USA) state that the US fusion programme has long recognized that the S

Chemical engineering side of nuclear fusion power

International Nuclear Information System (INIS)

Johnson, E.F.

1976-10-01

It is widely recognized that chemical engineering has important roles to play in the development of national and world wide energy resources through optimal utilization of fossil fuel reserves. It is much less appreciated that there are crucial chemical engineering problems in the development of energy production from other sources. In particular the successful development of nuclear fusion power generating systems will require the solution of many problems that are uniquely suited to chemical engineers. This article presents a brief overview of the fusion development program and an identification of the major technological problems remaining to be solved

Bringing fusion electric power closer

International Nuclear Information System (INIS)

Kintner, E.

1977-01-01

A review of the controlled fusion research program is given. The tokamak research program is described. Beam injection heating, control systems, and the safety of fusion reactors are topics that are also discussed

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

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

Fusion Simulation Program

International Nuclear Information System (INIS)

Greenwald, Martin

2011-01-01

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

Fusion power and its prospects

International Nuclear Information System (INIS)

Kammash, T.

1981-01-01

Recent progress in research towards the development of fusion power is reviewed. In the magnetic approach, the impressive advances made in Tokamak research in the past few years have bolstered the confidence that experimental Tokamak devices currently under construction will demonstrate the break-even condition or scientific feasibility of fusion power. Exciting and innovative ideas in mirror magnetic confinement are expected to culminate in high-Q devices which will make open-ended confinement a serious contender for fusion reactors. In the inertial confinement approach, conflicting pellet temperature requirements have placed severe constraints on useful laser intensities and wavelengths for laser-driven fusion. Relativistic electron beam fusion must solve critical focusing and pellet coupling problems, and the newly proposed heavy ion beam fusion, though feasible and attractive in principle, requires very high energy particles for which the accelerator technology may not be available for some time to come

Comparison of environmental impact of waste disposal from fusion, fission and coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Frey, Bruno [Fichtner GmbH und Co. KG, Stuttgart (Germany)

2011-08-15

The radiotoxic hazard of waste from fusion power plants has been compared with that of fission power and radioactive trace elements in coal ash within some research programs such as SEAFP and SEIF. Within another program, in 2005 a Power Plant Conceptual Study (PPCS) has been finalized investigating 4 fusion power plant models A to D. In this paper, the radiotoxicity of model B is compared with a fission power plant, concentrating on the production of wastes. The hazard of the respective masses of enriched uranium before use in a fission power plant and coal ash of a power plant generating the same amount of electricity are used as benchmarks. It is evident that the development of ingestion and inhalation hazard of the PPCS model B is different from the results of earlier studies because of different assumptions on material impurities and other constraints. An important aspect is the presence of actinides in fusion power plant waste. (orig.)

Fusion power research and development program. Volume IV. 5-year program, budget and milestone summaries

International Nuclear Information System (INIS)

1976-07-01

Budget data are given for each of the tokamak systems, mirror systems, and high density plasma systems for the years 1976 through 1982. All major facilities currently under ERDA contract are included. In addition, budget data are given for the development and technology program consisting of the following; (1) magnetic systems, (2) plasma engineering, (3) fusion reactor materials, (4) fusion systems engineering, (5) environment and safety, and (6) applied plasma physics

US-DOE Fusion-Breeder Program: blanket design and system performance

International Nuclear Information System (INIS)

Lee, J.D.

1983-01-01

Conceptual design studies are being used to assess the technical and economic feasibility of fusion's potential to produce fissile fuel. A reference design of a fission-suppressed blanket using conventional materials is under development. Theoretically, a fusion breeder that incorporates this fusion-suppressed blanket surrounding a 3000-MW tandem mirror fusion core produces its own tritium plus 5600 kg of 233 U per year. The 233 U could then provide fissile makeup for 21 GWe of light-water reactor (LWR) power using a denatured thorium fuel cycle with full recycle. This is 16 times the net electric power produced by the fusion breeder (1.3 GWe). The cost of electricity from this fusion-fission system is estimated to be only 23% higher than the cost from LWRs that have makeup from U 3 O 8 at present costs (55 $/kg). Nuclear performance, magnetohydrodynamics (MHD), radiation effects, and other issues concerning the fission-suppressed blanket are summarized, as are some of the present and future objectives of the fusion breeder program

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 core engineering for the ARIES-ST power plant

International Nuclear Information System (INIS)

Tillack, M.S.; Wang, X.R.; Pulsifer, J.; Malang, S.; Sze, D.K.; Billone, M.; Sviatoslavsky, I.

2003-01-01

ARIES-ST is a 1000 MWe fusion power plant based on a low aspect ratio 'spherical torus' (ST) plasma. The ARIES-ST power core was designed to accommodate the unique features of an ST power plant, to meet the top-level requirements of an attractive fusion energy source, and to minimize extrapolation from the fusion technology database under development throughout the world. The result is an advanced helium-cooled ferritic steel blanket with flowing PbLi breeder and tungsten plasma-interactive components. Design improvements, such as the use of SiC inserts in the blanket to extend the outlet coolant temperature range were explored and the results are reported here. In the final design point, the power and particle loads found in ARIES-ST are relatively similar to other advanced tokamak power plants (e.g. ARIES-RS [Fusion Eng. Des. 38 (1997) 3; Fusion Eng. Des. 38 (1997) 87]) such that exotic technologies were not required in order to satisfy all of the design criteria. Najmabadi and the ARIES Team [Fusion Eng. Des. (this issue)] provide an overview of ARIES-ST design. In this article, the details of the power core design are presented together with analysis of the thermal-hydraulic, thermomechanical and materials behavior of in-vessel components. Detailed engineering analysis of ARIES-ST TF and PF systems, nuclear analysis, and safety are given in the companion papers

Power source system for nuclear fusion

International Nuclear Information System (INIS)

Nakagawa, Satoshi.

1975-01-01

Object: When using an external system power source and an exclusive power source in a power source circuit for supplying power to the coils of a nuclear fusion apparatus, to minimize the capacity of the exclusive power source and provide an economical power source circuit construction. Structure: In the initial stage of the power supply, rectifying means provided in individual blocks are connected in parallel on the AC side, and power is supplied to the coils of the nuclear fusion apparatus from an external system power source with the exclusive power source held in the disconnected state. Further, at an instant when the limit of permissible input is reached, the afore-mentioned parallel circuit consisting of rectifying means is disconnected, while at the same time the exclusive power source is connected to the input side of the rectifying means provided in a block corresponding to the exclusive power source side, thereby supplying power to the coils of the nuclear fusion apparatus from both the external system power source and exclusive power source. (Kamimura, M.)

Review projects for the US Fusion Program: Progress report, December 1, 1984-February 28, 1987

International Nuclear Information System (INIS)

Ribe, F.L.

1988-01-01

This paper reviews projects at the University of Washington on the following topics: Magnetic Fusion Energy Program Plan (Feb. 1985); High Density Power Systems; Fusion Systems Studies; Burning Plasmas and Compact Ignition Tokamak; US Magnetic Mirror Program; and Technical Planning Activity (Jan. 1987)

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

Commercial objectives, technology transfer, and systems analysis for fusion power development

Science.gov (United States)

Dean, Stephen O.

1988-03-01

Fusion is an essentially inexhaustible source of energy that has the potential for economically attractive commercial applications with excellent safety and environmental characteristics. The primary focus for the fusion-energy development program is the generation of centralstation electricity. Fusion has the potential, however, for many other applications. The fact that a large fraction of the energy released in a DT fusion reaction is carried by high-energy neutrons suggests potentially unique applications. These include breeding of fissile fuels, production of hydrogen and other chemical products, transmutation or “burning” of various nuclear or chemical wastes, radiation processing of materials, production of radioisotopes, food preservation, medical diagnosis and medical treatment, and space power and space propulsion. In addition, fusion R&D will lead to new products and new markets. Each fusion application must meet certain standards of economic and safety and environmental attractiveness. For this reason, economics on the one hand, and safety and environment and licensing on the other hand, are the two primary criteria for setting long-range commercial fusion objectives. A major function of systems analysis is to evaluate the potential of fusion against these objectives and to help guide the fusion R&D program toward practical applications. The transfer of fusion technology and skills from the national laboratories and universities to industry is the key to achieving the long-range objective of commercial fusion applications.

Perspectives of fusion power

International Nuclear Information System (INIS)

Jensen, V.O.

1984-01-01

New and practically inexhaustible sources of energy must be developed for the period when oil, coal and uranium will become scarce and expensive. Nuclear fusion holds great promise as one of these practically inexhaustible energy sources. Based on the deuteriumtritium reaction with tritium obtained from naturally occuring lithium, which is also widely available in Europe, the accessible energy resources in the world are 3.10 12 to 3.10 16 toe; based on the deuterium-deuterium reaction, the deuterium content of the oceans corresponds to 10 20 toe. It is presently envisaged that in order to establish fusion as a large-scale energy source, three major thresholds must be reached: - Scientific feasibility, - Technical feasibility, i.e. the proof that the basic technical problems of the fusion reactor can be solved. - Commercial feasibility, i.e. proof that fusion power reactors can be built on an industrial scale, can be operated reliably and produce usable energy at prices competitive with other energy sources. From the above it is clear that the route to commercial fusion will be long and costly and involve the solution of extremely difficult technical problems. In view of the many steps which have to be taken, it appears unlikely that commercial fusion power will be in general use within the next 50 years and by that time world-wide expenditure on research, development and demonstration may well have exceeded 100 Bio ECU. (author)

The heavy ion fusion program in the USA

International Nuclear Information System (INIS)

Bangerter, R.O.; Davidson, R.C.; Herrmannsfeldt, W.B.; Lindl, J.; Meier, W.R.; Logan, B.G.

2001-01-01

Inertial fusion energy research has enjoyed increased interest and funding. This has allowed expanded programs in target design, target fabrication, fusion chamber research, target injection and tracking, and accelerator research. The target design effort examines ways to minimize the beam power and energy and increase the allowable focal spot size while preserving target gain. Chamber research for heavy ion fusion emphasizes the use of thick liquid walls to serve as the coolant, breed tritium, and protect the structural wall from neutrons, photons, and other target products. Several small facilities are now operating to model fluid chamber dynamics. A facility to study target injection and tracking has been built and a second facility is being designed. Improved economics is an important goal of the accelerator research. The accelerator research is also directed toward the design of an Integrated Research Experiment (IRE). The IRE is being designed to accelerate ions to >100 MeV, enabling experiments in beam dynamics, focusing, and target physics. Activities leading to the IRE include ion source development and a High Current Experiment (HCX) designed to transport and accelerate a single beam of ions with a beam current of approximately 1 A, the initial current required for each beam of a fusion driver. In terms of theory, the program is developing a source-to-target numerical simulation capability. The goal of the entire program is to enable an informed decision about the promise of heavy ion fusion in about a decade. (author)

Fusion Energy Postdoctoral Research Program, Professional Development Program: FY 1987 annual report

International Nuclear Information System (INIS)

1988-01-01

In FY 1986, Oak Ridge Associated Universities (ORAU) initiated two programs for the US Department of Energy (DOE), Office of Fusion Energy (OFE): the Fusion Energy Postdoctoral Research Program and the Fusion Energy Professional Development Program. These programs provide opportunities to conduct collaborative research in magnetic fusion energy research and development programs at DOE laboratories and contractor sites. Participants become trained in advanced fusion energy research, interact with outstanding professionals, and become familiar with energy-related national issues while making personal contributions to the search for solutions to scientific problems. Both programs enhance the national fusion energy research and development effort by providing channels for the exchange of scientists and engineers, the diffusion of ideas and knowledge, and the transfer of relevant technologies. These programs, along with the Magnetic Fusion Energy Science and Technology Fellowship Programs, compose the fusion energy manpower development programs administered by ORAU for DOE/OFE

Reduced activation structural materials for fusion power plants - The European Union program

International Nuclear Information System (INIS)

Schaaf, B. van der; Le Marois, G.; Moeslang, A.; Victoria, M.

2003-01-01

The competition of fusion power plants with the renewable energy sources in the second half of the 21st century requires structural materials operating at high temperatures, and sufficient radiation resistance to ensure high plant efficiency and availability. The reduced activation materials development in the EU counts several steps regarding the radiation damage resistance: 75 dpa for DEMO and 150 dpa and beyond for power plants. The maximum operating temperature development line ranges from the present day from the present day feasible 600 K up to 1300- K in advanced power plants. The reduced activation steel, RAS, forms the reference for the development efforts. EUROFER has been manufactured in the EU on industrial scale with specified purity and mechanical properties up to 825 K. The oxide dispersion strengthened , ODS, variety of RAS should reach the 925 K operation limit. The EU has selected silicon carbide ceramic composite as the primary high temperature, 1300 K, goal. On a small scale the potential of tungsten alloys for higher temperatures is investigated. The present test environments for radiation resistance are insufficient to provide data for DEMO. Hence the support of the EU for the International Fusion Materials Irradiation facility. The computational modelling is expected to guide the materials development and the design of near plasma components. The EU co-operates closely with Japan, the RF and US in IEA and IAEA co-ordinated agreements, which are highly beneficial for the fusion structural materials development. (author)

Fusion

CERN Document Server

Mahaffey, James A

2012-01-01

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

Net energy balance of tokamak fusion power plants

International Nuclear Information System (INIS)

Buende, R.

1983-01-01

The net energy balance for a tokamak fusion power plant of present day design is determined by using a PWR power plant as reference system, replacing the fission-specific components by fusion-specific components and adjusting the non-reactor-specific components to altered conditions. For determining the energy input to the fusion plant a method was developed that combines the advantages of the energetic input-output method with those of process chain analysis. A comparison with PWR, HTR, FBR, and coal-fired power plants is made. As a result the energy expenditures of the fusion power plant turn out to be lower than that of an LWR, HTR, or coal-fired power plant of equal net electric power output and nearly in the same range as FBR power plants. (orig.)

Net energy balance of tokamak fusion power plants

International Nuclear Information System (INIS)

Buende, R.

1981-10-01

The net energy balance for a tokamak fusion power plant was determined by using a PWR power plant as reference system, replacing the fission-specific components by fusion-specific components and adjusting the non-reactor-specific components to altered conditions. For determining the energy input to the fusion plant a method was developed that combines the advantages of the energetic input-output method with those of process chain analysis. A comparison with PWR, HTR, FBR, and coal-fired power plants is made. As a result the net energy balance of the fusion power plant turns out to be more advantageous than that of an LWR, HTR or coal-fired power plant and nearly in the same range as FBR power plants. (orig.)

Evaluation of divertor conceptual designs for a fusion power plant

International Nuclear Information System (INIS)

Ferrari, M.; Giancarli, L.; Kleefeldt, K.; Nardi, C.; Roedig, M.; Reimann, J.; Salavy, J.F.

2001-01-01

In the frame of the preliminary study of plants suitable for the energy production from the fusion power, particular emphasis has been given on the divertor studies. Since a significant percentage of the power generated from the fusion process is absorbed in the divertor, the thermal efficiency of the power conversion cycle requires a high coolant outlet temperature of the divertor, leading to solutions that are different from those adopted for the present experimental fusion plants. Therefore, copper alloys having extremely high thermal conductivity, cannot be used as structural material for this kind of devices. The most suitable coolants to be used in the divertor are water, helium and liquid metals. A conceptual design study has been developed for each of these three fluids, with the aim to evaluate the maximum allowable thermal flux at the divertor target plate and the R and D requirements for each solution. While a water-cooled divertor can be designed with a limited R and D effort, the development of helium or liquid metal cooled divertors requires a more engaging R and D program

Current fusion power plant design concepts

International Nuclear Information System (INIS)

Gore, B.F.; Murphy, E.S.

1976-09-01

Nine current U.S. designs for fusion power plants are described in this document. Summary tabulations include a tenth concept, for which the design document was unavailable during preparation of the descriptions. The information contained in the descriptions was used to define an envelope of fusion power plant characteristics which formed the basis for definition of reference first commercial fusion power plant design. A brief prose summary of primary plant features introduces each of the descriptions contained in the body of this document. In addition, summary tables are presented. These tables summarize in side-by-side fashion, plant parameters, processes, combinations of materials used, requirements for construction materials, requirements for replacement materials during operation, and production of wastes

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.

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 power plant simulations: a progress report

International Nuclear Information System (INIS)

Cook, J.M.; Pattern, J.S.; Amend, W.E.

1976-01-01

The objective of the fusion systems analysis at ANL is to develop simulations to compare alternative conceptual designs of magnetically confined fusion power plants. The power plant computer simulation progress is described. Some system studies are also discussed

Pinch me - I'm fusing. Fusion Power - what is it? What is a z pinch? And why are z-pinches a promising fusion power technology?

International Nuclear Information System (INIS)

DERZON, MARK S.

2000-01-01

The process of combining nuclei (the protons and neutrons inside an atomic nucleus) together with a release of kinetic energy is called fusion. This process powers the Sun, it contributes to the world stockpile of weapons of mass destruction and may one day generate safe, clean electrical power. Understanding the intricacies of fusion power, promised for 50 years, is sometimes difficult because there are a number of ways of doing it. There is hot fusion, cold fusion and con-fusion. Hot fusion is what powers suns through the conversion of mass energy to kinetic energy. Cold fusion generates con-fusion and nobody really knows what it is. Even so, no one is generating electrical power for you and me with either method. In this article the author points out some basic features of the mainstream approaches taken to hot fusion power, as well as describe why z pinches are worth pursuing as a driver for a power reactor and how it may one day generate electrical power for mankind

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

Power matching for pellet fusion

International Nuclear Information System (INIS)

Martin, R.L.; Arnold, R.C.

1976-01-01

The number of beams required for optimum power transfer from a given power source to the surface of a pellet is derived. The result is valid for linear optical systems, hence, for pellet fusion by laser or high energy ion beams. The optimum number of beams turns out to be inconceivably large for any practical system. Practical pellet fusion by lasers or high energy heavy ion beams must thus compromise physical principles in favor of reduced cost and optical complexity

Inertial Fusion Power Plant Concept of Operations and Maintenance

Energy Technology Data Exchange (ETDEWEB)

Anklam, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Knutson, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dunne, A. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kasper, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sheehan, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lang, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Roberts, V. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mau, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-01-15

Parsons and LLNL scientists and engineers performed design and engineering work for power plant pre-conceptual designs based on the anticipated laser fusion demonstrations at the National Ignition Facility (NIF). Work included identifying concepts of operations and maintenance (O&M) and associated requirements relevant to fusion power plant systems analysis. A laser fusion power plant would incorporate a large process and power conversion facility with a laser system and fusion engine serving as the heat source, based in part on some of the systems and technologies advanced at NIF. Process operations would be similar in scope to those used in chemical, oil refinery, and nuclear waste processing facilities, while power conversion operations would be similar to those used in commercial thermal power plants. While some aspects of the tritium fuel cycle can be based on existing technologies, many aspects of a laser fusion power plant presents several important and unique O&M requirements that demand new solutions. For example, onsite recovery of tritium; unique remote material handling systems for use in areas with high radiation, radioactive materials, or high temperatures; a five-year fusion engine target chamber replacement cycle with other annual and multi-year cycles anticipated for major maintenance of other systems, structures, and components (SSC); and unique SSC for fusion target waste recycling streams. This paper describes fusion power plant O&M concepts and requirements, how O&M requirements could be met in design, and how basic organizational and planning issues can be addressed for a safe, reliable, economic, and feasible fusion power plant.

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

The ORNL fusion power demonstration study

International Nuclear Information System (INIS)

Shannon, T.E.; Steiner, D.

1978-01-01

In this paper, we review the design approach developed in the ORNL Fusion Power Demonstration Study [1]. The major emphasis of this study is in the application of current and near-term technology as the most logical path to near-term demonstration of tokamak fusion power. In addition we are pursuing a number of concepts to simplify the tokamak reactor to be more acceptable to the utility industry as a future source of energy. The discussion will focus on the areas having the greatest overall impact on reactor feasibility: 1) overall size and power output, 2) remote maintenance considerations, 3) electrical power supplies, 4) blanket design; and 5) economics. The tokamak device, by nature of its configuration and pulsed operation, is an exceptionally complex engineering design problem. We have concluded that innovative design concepts are essential to cope with this basic complexity. We feel that the feasibility of tokamak fusion power has been significantly improved by these design approaches. (author)

Pulsed power ion accelerators for inertially confined fusion

International Nuclear Information System (INIS)

Olson, C.L.

1976-01-01

Current research is described on pulsed power ion accelerators for inertial fusion, i.e., ion diodes and collective accelerators. Particle beam energy and power requirements for fusion, and basic deposition characteristics of charged particle beams are discussed. Ion diodes and collective accelerators for fusion are compared with existing conventional accelerators

Fusion research activities in China

International Nuclear Information System (INIS)

Deng Xiwen

1998-01-01

The fusion program in China has been executed in most areas of magnetic confinement fusion for more than 30 years. Basing on the situation of the power supply requirements of China, the fusion program is becoming an important and vital component of the nuclear power program in China. This paper reviews the status of fusion research and next step plans in China. The motivation and goal of the Chinese fusion program is explained. Research and development on tokamak physics and engineering in the southwestern institute of physics (SWIP) and the institute of plasma physics of Academic Sinica (ASIPP) are introduced. A fusion breeder program and a pure fusion reactor design program have been supported by the state science and technology commission (SSTC) and the China national nuclear corporation (CNNC), respectively. Some features and progress of fusion reactor R and D activities are reviewed. Non fusion applications of plasma science are an important part of China fusion research; a brief introduction about this area is given. Finally, an introductional collaboration network on fusion research activities in China is reported. (orig.)

Technology spin-offs from the magnetic fusion energy program

International Nuclear Information System (INIS)

1982-05-01

A description is given of 138 possible spin-offs from the magnetic fusion program. The spin-offs cover the following areas: (1) superconducting magnets, (2) materials technology, (3) vacuum systems, (4) high frequency and high power rf, (5) electronics, (6) plasma diagnostics, (7) computers, and (8) particle beams

Fusion power plant studies in Europe

International Nuclear Information System (INIS)

Maisonnier, D.

2007-01-01

The European fusion programme is reactor oriented and it is aimed at the successive demonstration of the scientific, the technological and the economic feasibility of fusion power. For a reactor-oriented fusion development programme, it is essential to have a clear idea of the ultimate goal of the programme, namely a series of models of fusion power plants, in order to define the correct strategy and to assess the pertinence of the on-going activities. The European Power Plant Conceptual Study (PPCS) has been a study of conceptual designs for commercial fusion power plants. It focused on five power plant models, named PPCS A, B, AB, C and D, which are illustrative of a wider spectrum of possibilities. They are all based on the tokamak concept and they have approximately the same net electrical power output, 1500 MWe. These span a range from relatively near-term, based on limited technology and plasma physics extrapolations, to an advanced conception. All five PPCS plant models differ substantially from the models that formed the basis of earlier European studies. They also differ from one another, which lead to differences in economic performance and in the details of safety and environmental impacts. The main emphasis of the PPCS was on system integration. Systems analyses were used to produce self-consistent plant parameter sets with approximately optimal economic characteristics for all models. In the PPCS models, the favourable, inherent, features of fusion have been exploited to provide substantial safety and environmental advantages. The broad features of the safety and environmental conclusions of previous studies have been confirmed and demonstrated with increased confidence. The PPCS study highlighted the need for specific design and R and D activities, in addition to those already underway within the European long term R and D programme, as well as the need to clarify the concept of DEMO, the device that will bridge the gap between ITER and the first

Technical review of the Sandia Laboratories' Particle Beam Fusion Program

International Nuclear Information System (INIS)

1979-01-01

This report considers the technical aspects of Sandia Laboratories' Particle Beam Fusion Program and examines the program's initial goals, the progress made to date towards reaching those goals, and the future plans or methods of reaching those original or modified goals. A summary of Sandia Laboratories' effort, which seeks to demonstrate that high voltage pulsed power generated high-current electron or light ion beams can be used to ignite a deuterium or tritium pellet, is provided. A brief review and assessment of the Sandia Pulse Power Program is given. Several critical issues and summaries of the committee members' opinions are discussed

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

Fast power cycle for fusion reactors

International Nuclear Information System (INIS)

Powell, J.; Fillo, J.; Makowitz, H.

1978-01-01

The unique, deep penetration capability of 14 MeV neutrons produced in DT fusion reactions allows the generation of very high temperature working fluid temperatures in a thermal power cycle. In the FAST (Fusion Augmented Steam Turbine) power cycle steam is directly superheated by the high temperature ceramic refractory interior of the blanket, after being generated by heat extracted from the relatively cool blanket structure. The steam is then passed to a high temperature gas turbine for power generation. Cycle studies have been carried out for a range of turbine inlet temperatures [1600 0 F to 3000 0 F (870 to 1650 0 C)], number of reheats, turbine mechanical efficiency, recuperator effectiveness, and system pressure losses. Gross cycle efficiency is projected to be in the range of 55 to 60%, (fusion energy to electric power), depending on parameters selected. Turbine inlet temperatures above 2000 0 F, while they do increase efficiency somewhat, are not necessarily for high cycle efficiency

Materials availability for fusion power plant construction

International Nuclear Information System (INIS)

Hartley, J.N.; Erickson, L.E.; Engel, R.L.; Foley, T.J.

1976-09-01

A preliminary assessment was made of the estimated total U.S. material usage with and without fusion power plants as well as the U.S. and foreign reserves and resources, and U.S. production capacity. The potential environmental impacts of fusion power plant material procurement were also reviewed including land alteration and resultant chemical releases. To provide a general measure for the impact of material procurement for fusion reactors, land requirements were estimated for mining and disposing of waste from mining

Fuel procurement for first generation fusion power plants

International Nuclear Information System (INIS)

Gore, B.F.; Hendrickson, P.L.

1976-09-01

The provision of deuterium, tritium, lithium and beryllium fuel materials for fusion power plants is examined in this document. Possible fusion reactions are discussed for use in first generation power plants. Requirements for fuel materials are considered. A range of expected annual consumption is given for each of the materials for a 1000 megawatts electric (MWe) fusion power plant. Inventory requirements are also given. Requirements for an assumed fusion power plant electrical generating capacity of 10 6 MWe (roughly twice present U.S. generating capacity) are also given. The supply industries are then examined for deuterium, lithium, and beryllium. Methods are discussed for producing the only tritium expected to be purchased by a commercial fusion industry--an initial inventory for the first plant. Present production levels and methods are described for deuterium, lithium and beryllium. The environmental impact associated with production of these materials is then discussed. The toxicity of beryllium is described, and methods are indicated to keep worker exposure to beryllium as low as achievable

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

International Nuclear Information System (INIS)

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

2006-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-06-07

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

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)

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

Synfuel (hydrogen) production from fusion power

International Nuclear Information System (INIS)

Krakowski, R.A.; Cox, K.E.; Pendergrass, J.H.; Booth, L.A.

1979-01-01

A potential use of fusion energy for the production of synthetic fuel (hydrogen) is described. The hybrid-thermochemical bismuth-sulfate cycle is used as a vehicle to assess the technological and economic merits of this potential nonelectric application of fusion power

Advanced fusion concepts program

International Nuclear Information System (INIS)

Dove, W.F.

1978-01-01

While the prospects for the eventual development of a tokamak-based fusion reactor appear promising at the present time, the Department of Energy maintains a vigorous program in alternate magnetic fusion concepts. Several of the concepts presently supported include the toroidal reversed field pinch, Tormac, Elmo Bumpy Torus, and various linear options. Recent technical accomplishments and program evaluations indicate that the possibility now exists for undertaking the next development stage, a proof-of-principle experiment, for a few of the most promising alternate concepts

Environmental cost/benefit analysis for fusion power plants

International Nuclear Information System (INIS)

Young, J.R.

1976-11-01

This document presents a cost/benefit analysis of use of fusion power plants early in the 21st century. The first section describes the general formulation of the analysis. Included are the selection of the alternatives to the fusion reactor, selection of the power system cases to be compared, and a general comparison of the environmental effects of the selected alternatives. The second section compares the cumulative environmental effects from 2010 to 2040 for the primary cases of the power system with and without fusion reactors. The third section briefly illustrates the potential economic benefits if fusion reactors produce electricity at a lower unit cost than LMFBRs can. The fourth section summarizes the cost/benefit analysis

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

Optimization of nonthermal fusion power consistent with channeling of charged fusion product energy

International Nuclear Information System (INIS)

Snyder, P.B.; Herrmann, M.C.; Fisch, N.J.

1994-01-01

If the energy of charged fusion products can be diverted directly to fuel ions, non-Maxwellian fuel ion distributions and temperature differences between species will result. To determine the importance of these nonthermal effects, the fusion power density is optimized at constant-β for non-thermal distributions that are self-consistently maintained by channeling of energy from charged fusion products. For D-T and D- 3 He reactors, with 75% of charged fusion product power diverted to fuel ions, temperature differences between electrons and ions increase the reactivity by 40-70%, while non-Maxwellian fuel ion distributions and temperature differences between ionic species increase the reactivity by an additional 3-15%

The spherical tokamak fusion power plant

International Nuclear Information System (INIS)

Wilson, H.R.; Voss, G.; Ahn, J.W.

2003-01-01

The design of a 1GW(e) steady state fusion power plant, based on the spherical tokamak concept, has been further iterated towards a fully self-consistent solution taking account of plasma physics, engineering and neutronics constraints. In particular a plausible solution to exhaust handling is proposed and the steam cycle refined to further improve efficiency. The physics design takes full account of confinement, MHD stability and steady state current drive. It is proposed that such a design may offer a fusion power plant which is easy to maintain: an attractive feature for the power plants following ITER. (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

Prospects for commercial fusion power

International Nuclear Information System (INIS)

Dean, S.O.

1993-01-01

There are a number of issues associated with whether or not, and when, fusion will become commercial. One of the largest factors is cost of development. Development is being delayed by the need to work with other countries to share these costs. Other aspects have to do with the capital costs of the reactors themselves. The ITER reactor may cost 6-7 billion dollars, which is a sizeable investment for a test reactor. The safety and environmental aspects of fusion are other factors which have delayed commercialization. Public acceptance of this form of nuclear power and the licensing and regulatory procedures must be resolved before electric utilities are willing to invest heavily in fusion. The Department of Energy has developed a plan as part of the Energy Policy Act of 1992, wherein a first demonstration power plant will be operating around the year 2025. Much of the ongoing effort is directed toward reducing the size and cost of Tokamak reactors. While Tokamaks are not the only game in town, it is the primary thrust of the world effort and it is the technology which is expected to lead into the first generation of commercial fusion reactors

Overview of US heavy-ion fusion commercial electric power systems assessment project. Revision

International Nuclear Information System (INIS)

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

1986-01-01

The US heavy-ion fusion (HIF) research program is oriented toward development of multiple-beam induction linacs. Over the last two years an assessment has been performed of the potential of HIF as a competitive commercial electric power source. This assessment involved several technology performance and cost issues (e.g., final beam transport system, target manufacturing, beam stability in reactor cavity environments, and reactor cavity clearing), as well as overall power plant systems integration and tradeoff studies. Results from parametric analyses using a systems code developed in the project show cost of electricity (COE) values comparable with COEs from other magnetic fusion and inertial confinement fusion (ICF) plant studies; viz, 50-60 mills/kWh (1985 dollars) for 1-GWe plants. Also, significant COE insensitivity to major accelerator, target, and reactor parameters was demonstrated

A fusion engineering program for Canada

International Nuclear Information System (INIS)

Billington, I.J.

In 1980 the National Research Council asked DSMA ATCON Ltd., in collaboration with Ontario Hydro, the University of Toronto, and McMaster University, to evaluate concepts for a national fusion engineering program, to define a facility that could be constructed in Canada to meet the program goals, and to suggest a strategy for encouraging industrial participation. The central element of the proposed fusion engineering and development program is tritium technology, with additional emphasis on the broader field of all hydrogen isotopes and their interactions with materials. The Canadian program in the initial phase would concentrate on fusion fuel systems, materials development, equipment development, and safety and the environment. A preliminary concept for the facility required has been developed, and key organizational activities identified. The total program costs should be $1 million in the first year, rising to a steady state of $5 million from the fourth year onward. The capital cost of the research facility is estimated to be $20 million spread over three years, and its operating budget around $7 million. The program as envisioned would make use of Canada's existing tritium resources and handling experience to contribute to worldwide fusion research

Implications of fusion power plant studies for materials requirements

International Nuclear Information System (INIS)

Cook, Ian; Ward, David; Dudarev, Sergei

2002-01-01

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

Why and how of fusion

International Nuclear Information System (INIS)

Miley, G.H.

1977-01-01

The potential advantages of fusion power are listed. The approaches to plasma containment are mentioned and the status of the fusion program is described. The ERDA and EPRI programs are discussed. The Fusion Energy Foundation's activities are mentioned. Fusion research at the U. of Ill. is described briefly

The Heavy Ion Fusion Program in the U.S.A

International Nuclear Information System (INIS)

Bangerter, R.O.; Davidson, R.C.; Herrmannsfeldt, W.B.; Lindl, J.D.; Logan, B.G.; Meier, W.R.

2000-01-01

Inertial fusion energy research has enjoyed increased interest and funding. This has allowed expanded programs in target design, target fabrication, fusion chamber research, target injection and tracking, and accelerator research. The target design effort examines ways to minimize the beam power and energy and increase the allowable focal spot size while preserving target gain. Chamber research for heavy ion fusion emphasizes the use of thick liquid walls to serve as the coolant, breed tritium, and protect the structural wall from neutrons, photons, and other target products. Several small facilities are now operating to model fluid chamber dynamics. A facility to study target injection and tracking has been built and a second facility is being designed. Improved economics is an important goal of the accelerator research. The accelerator research is also directed toward the design of an Integrated Research Experiment (IRE). The IRE is being designed to accelerate ions to >100 MeV, enabling experiments in beam dynamics, focusing, and target physics. Activities leading to the IRE include ion source development and a High Current Experiment (HCX) designed to transport and accelerate a single beam of ions with a beam current of approximately 1 A, the initial current required for each beam of a fusion driver. In terms of theory, the program is developing a source-to-target numerical simulation capability. The goal of the entire program is to enable an informed decision about the promise of heavy ion fusion in about a decade

Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

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

1995-12-01

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

The plant efficiency of fusion power stations

International Nuclear Information System (INIS)

Darvas, J.; Foerster, S.

1976-01-01

Due to the circulating energy, lower efficiencies are to be expected with fusion power plants than with nuclear fission power plants. According to the systems analysis, the mirror machine is not very promising as a power plant. The plant efficiency of the laser fusion strongly depends on the laser efficiency about which one can only make speculative statements at present. The Tokamak requires a relatively low circulating energy and is certainly able to compete regarding efficiency as long as the consumption time can be kept large (> 100 sec) and the dead time between the power pulses small ( [de

Science assessment of fusion power plant

International Nuclear Information System (INIS)

Nagai, Toru; Shimazu, Yasuo

1984-01-01

A concept of SCIENCE ASSESSMENT (SA) is proposed to support a research program of the so-called big science. The SA System should be established before the demonstration reactor is realized, and the system is classified into four categories: (1) Resource Economy Assessment (REA) (cost evaluation and availability of rare resource materials), (2) Risk Assessment (RA) (structural safety during operation and accident), (3) Environmental Assessment (EA) (adaptability to environments), and (4) Socio-Political Assessment (SPA) (from local public acceptance to national policy acceptance). Here, REA to the published conceptual designs of commercial fusion power plants (most of them are TOKAMAK) is carried out as the first step. The energy analysis method is imployed because the final goal of fusion plant is to supply energy. The evaluation index is the energy ratio (= output/input). Computer code for energy analysis was developed, to which the material inventory table from the conceptual design and the database for the energy intensity (= energy required to obtain a unit amount of materials) were prepared. (Nogami, K.)

The fusion blanket program at Chalk River

International Nuclear Information System (INIS)

Hastings, I.J.

1986-03-01

Work on the Fusion Blanket Program commenced at Chalk River in 1984 June. Co-funded by Canadian Fusion Fuels Technology Project and Atomic Energy of Canada Limited, the Program utilizes Chalk River expertise in instrumented irradiation testing, ceramics, tritium technology, materials testing and compound chemistry. This paper gives highlights of studies to date on lithium-based ceramics, leading contenders for the fusion blanket

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.

Indirect drive targets for fusion power

Energy Technology Data Exchange (ETDEWEB)

Amendt, Peter A.; Miles, Robin R.

2016-10-11

A hohlraum for an inertial confinement fusion power plant is disclosed. The hohlraum includes a generally cylindrical exterior surface, and an interior rugby ball-shaped surface. Windows over laser entrance holes at each end of the hohlraum enclose inert gas. Infrared reflectors on opposite sides of the central point reflect fusion chamber heat away from the capsule. P2 shields disposed on the infrared reflectors help assure an enhanced and more uniform x-ray bath for the fusion fuel capsule.

Pulsed power for fusion

International Nuclear Information System (INIS)

Martin, T.H.

1976-01-01

A review which traces the development of high power pulsed accelerators from the original inception at the Atomic Weapons Research Establishment, Aldermaston, England, for Bremsstrahlung output, through the low impedance accelerators, to the double-sided accelerators for fusion will be given. Proto II is presently being assembled at Sandia and preliminary testing on the Marx has been completed. Examples of various techniques will be shown from Sandia accelerators. Requirements for accelerators capable of achieving fusion levels will be developed and problem areas outlined. The diode insulator flashover problem presently limits the maximum current available from the accelerators

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)

Fusion power plant for water desalination and reuse

International Nuclear Information System (INIS)

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

2001-01-01

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

Fusion power plant for water desalination and reuse

Energy Technology Data Exchange (ETDEWEB)

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

2001-11-01

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

Fusion Safety Program annual report, fiscal year 1994

International Nuclear Information System (INIS)

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

1995-03-01

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

The US fusion materials program: Status and directions

International Nuclear Information System (INIS)

Doran, D.G.

1987-05-01

The general long term objective of the Fusion Materials Program of the Office of Fusion Energy is the development of new or improved materials that will enhance the economic and environmental attractiveness of fusion as an energy source. The US Magnetic Fusion Program Plan, as augmented by the Technical Planning Activity (TPA), calls for information to be developed on critical issues such that a decision can be made by about 2005 on whether to pursue fusion as a viable energy source. Viability will be evaluated in at least four areas: technical, economic, environmental, and safety. The Fusion Materials Program addresses directly only the magnetic confinement option, although some of the information gained is applicable to the alternative approach of inertial confinement. The scope of this paper is limited to programs in which a primary concern is bulk neutron radiation effects, as opposed to those in which the primary concern is interaction of the materials with the plasma. 14 refs

Progress in pulsed power fusion

Energy Technology Data Exchange (ETDEWEB)

Quintenz, J P; Adams, R G; Bailey, J E [Sandia Labs., Albuquerque, NM (United States); and others

1997-12-31

Pulsed power offers an efficient, high energy, economical source of x-rays for inertial confinement fusion (ICF) research. Two main approaches to ICF driven with pulsed power accelerators are pursued: intense light ion beams and z-pinches. Recent progress in each approach and plans for future development is described. (author). 2 figs., 10 refs.

Progress in pulsed power fusion

International Nuclear Information System (INIS)

Quintenz, J.P.; Adams, R.G.; Bailey, J.E.

1996-01-01

Pulsed power offers an efficient, high energy, economical source of x-rays for inertial confinement fusion (ICF) research. Two main approaches to ICF driven with pulsed power accelerators are pursued: intense light ion beams and z-pinches. Recent progress in each approach and plans for future development is described. (author). 2 figs., 10 refs

Overview of US Fusion Energy Programs: January 1993

International Nuclear Information System (INIS)

Crandall, D.H.

1994-01-01

The US Fusion Program is in open-quotes Transition.close quotes This happens so infrequently that no one knows exactly what to expect; it makes everyone a little skittish. Program leadership does make a difference; Secretary Watkins was a positive force for fusion. Energy Research Director Happer remains in his position and is a positive force for scientific quality. Secretary O'Leary has stated that open-quotes Fusion energy holds great promise as an element of the nation's long-term energy supply.close quotes While new leaders may seek new directions with important implications for fusion, it seems reasonable to expect that, for fusion, such changes are likely to emerge slowly. Thus the assumption now is that the fusion priorities remain unchanged. In the spirit of optimism surrounding the new administration, the Fusion Energy Program's intention is to make as much progress as possible on the course presently established

Panel discussion on prospects for fusion power

International Nuclear Information System (INIS)

Sheffield, J.

1986-01-01

Although substantial progress is made every year in fusion research, the projected time to realize the ultimate goal of commercial fusion always seems to be 25 to 30 years away. This shifting schedule reflects the underlying difficulty of developing fusion. Every new technology improves the prospects for success, yet as each fusion mountain is scaled, it serves mainly to bring a better view of the next mountain. Two questions are considered: (1) why are so many configurations studied, and (2) what constitutes an economic power density

Fusion Canada issue 18

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-08-01

A short bulletin from the National Fusion Program. Included in this issue is a report on the ITER agreement signed with the EDA, the robotic maintenance for NET, the CFFTP Fusion Pilot Study, the new IEA joint programs on environment, safety and economic aspects of fusion power, and a review by the CCFM advisory committee. 3 figs.

Fusion Canada issue 18

International Nuclear Information System (INIS)

1992-08-01

A short bulletin from the National Fusion Program. Included in this issue is a report on the ITER agreement signed with the EDA, the robotic maintenance for NET, the CFFTP Fusion Pilot Study, the new IEA joint programs on environment, safety and economic aspects of fusion power, and a review by the CCFM advisory committee. 3 figs

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

The road to sustainable fusion power

International Nuclear Information System (INIS)

Meade, D.M.

1996-01-01

Fusion energy has the potential to provide a vital, environmentally attractive energy option for a growing world population in the next century and beyond. While the development of a new energy source is not a critical near term need for the US, there is a need to develop long-term energy options that alleviate the environmental problems associated with fossil fuels. Presently, a world-wide fusion energy R and D program is working toward the goal of establishing the scientific and technological foundations for fusion energy. This paper will concentrate on issues related to determining the scientific feasibility of fusion using magnetic confinement

Magnetic Fusion Energy Technology Fellowship Program: Summary of program activities for calendar year 1985

International Nuclear Information System (INIS)

1985-01-01

This report summarizes the activities of the US Department of Energy (DOE) Magnetic Fusion Energy Technology Fellowship program (MFETF) for the 1985 calendar year. The MFETF program has continued to support the mission of the Office of Fusion Energy (OFE) and its Division of Development and Technology (DDT) by ensuring the availability of appropriately trained engineering manpower needed to implement the OFE/DDT magnetic fusion energy agenda. This program provides training and research opportunities to highly qualified students at DOE-designated academic, private sector, and government magnetic fusion energy institutions. The objectives of the Magnetic Fusion Energy Technology Fellowship program are: (1) to provide support for graduate study, training, and research in magnetic fusion energy technology; (2) to ensure an adequate supply of appropriately trained manpower to implement the nation's magnetic fusion energy agenda; (3) to raise the visibility of careers in magnetic fusion energy technology and to encourage students to pursue such careers; and (4) to make national magnetic fusion energy facilities available for manpower training

The restructured fusion program and the role of alternative fusion concepts

International Nuclear Information System (INIS)

Perkins, L.J.

1996-01-01

This testimony to the subcommittee on Energy and the Environment of the U.S. House of Representatives's Committee on Science pushes for about 25% of the fusion budget to go to alternative fusion concepts. These concepts are: low density magnetic confinement, inertial confinement fusion, high density magnetic confinement, and non- thermonuclear and miscellaneous programs. Various aspects of each of these concepts are outlined

Status of inertial fusion

International Nuclear Information System (INIS)

Keefe, D.

1987-04-01

The technology advancement to high-power beams has also given birth to new technologies. That class of Free Electron Lasers that employs rf linacs, synchrotrons, and storage rings - although the use the tools of High Energy Physics (HEP) - was developed well behind the kinetic energy frontier. The induction linac, however, is something of an exception; it was born directly from the needs of the magnetic fusion program, and was not motivated by a high-energy physics application. The heavy-ion approach to inertial fusion starts with picking from the rich menu of accelerator technologies those that have, ab initio, the essential ingredients needed for a power plant driver: multigap acceleration - which leads to reliability/lifetime; electrical efficiency; repetition rate; and beams that can be reliably focused over a suitably long distance. The report describes the programs underway in Heavy Ion Fusion Accelerator Research as well as listing expected advances in driver, target, and beam quality areas in the inertial fusion power program

Technology assessment of laser-fusion power production

International Nuclear Information System (INIS)

Booth, L.A.; Frank, T.G.

1976-01-01

The inherent features of laser-induced fusion, some laser-fusion reactor concepts, and attendant means of utilizing the thermonuclear energy for commercial electric power generation are discussed. Theoretical fusion-pellet microexplosion energy release characteristics are described and the effects of pellet design options on pellet-microexplosion characteristics are discussed. The results of analyses to assess the engineering feasibility of reactor cavities for which protection of cavity components is provided either by suitable ablative materials or by diversion of plasmas by magnetic fields are presented. Two conceptual laser-fusion electric generating stations, based on different laser-fusion reactor concepts, are described. Technology developments for ultimate commercial application are outlined

The U.S. program for fusion nuclear technology development

International Nuclear Information System (INIS)

Clarke, J.F.; Haas, G.M.

1989-01-01

The Fusion Nuclear Technology (FNT) research and development program in the United States is shaped by a hierarchy of documents and by the environment for nuclear energy existing in the United States. The fission nuclear industry in the United States has suffered problems with public perception of safety, waste disposal issues, and economics as influenced by safety and environmental issues. For fusion to be a viable energy alternative, it must offer significant improvements in these areas. The hierarchy of documents defining objectives, plans, and strategy of the U.S. FNT program consists of the Magnetic Fusion Program Plan (MFPP) (February 1985), the Technical Planning Activity Final Report (January 1987), the Finesse Program Report (January 1987), and the Blanket Comparison and Selection Study Final Report (September 1984). In addition, two other documents are also significant in shaping FNT policy. These are the IEA report on Material for Fusion (December 1986) and the Summary of the Report of the Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (September 1987). The U.S. Magnetic Fusion Program Plan defines four key technical issues (magnetic confinement systems, properties of burning plasmas, fusion nuclear technology, and fusion materials). (orig./KP)

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

Methodology for Scaling Fusion Power Plant Availability

International Nuclear Information System (INIS)

Waganer, Lester M.

2011-01-01

Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, 'Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the 'teething' problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated 'mature' subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

Issues in radioactive waste management for fusion power

International Nuclear Information System (INIS)

Maninger, R.C.; Dorn, D.W.

1983-01-01

Analysis of recent conceptual designs reveals that commercial fusion power systems will raise issues of occupational and public health and safety. This paper focuses on radioactive wastes from fusion reactor materials activated by neutrons. The analysis shows that different selections of materials and neutronic designs can make differences in orders-of magnitude of the kinds and amounts of radioactivity to be expected. By careful and early evaluation of the impacts of the selections on waste management, designers can produce fusion power systems with radiation from waste well below today's limits for occupational and public health and safety

Issues in radioactive-waste management for fusion power

International Nuclear Information System (INIS)

Maninger, R.C.; Dorn, D.W.

1982-01-01

Analysis of recent conceptual designs reveals that commercial fusion power systems will raise issues of occupational and public health and safety. This paper focuses on radioactive wastes from fusion reactor materials activated by neutrons. The analysis shows that different selections of materials and neutronic designs can make differences in orders-of-magnitude of the kinds and amounts of radioactivity to be expected. By careful and early evaluation of the impacts of the selections on waste management, designers can produce fusion power systems with radiation from waste well below today's limits for occupational and public health and safety

Parameter study toward economical magnetic fusion power reactors

International Nuclear Information System (INIS)

Yoshida, Tomoaki; Okano, Kunihiko; Nanahara, Toshiya; Hatayama, Akiyoshi; Yamaji, Kenji; Takuma, Tadashi.

1996-01-01

Although the R and D of nuclear fusion reactors has made a steady progress as seen in ITER project, it has become of little doubt that fusion power reactors require hugeness and enormous amount of construction cost as well as surmounting the physics and engineering difficulties. Therefore, it is one of the essential issues to investigate the prospect of realizing fusion power reactors. In this report we investigated the effects of physics and engineering improvements on the economics of ITER-like steady state tokamak fusion reactors using our tokamak system and costing analysis code. With the results of this study, we considered what is the most significant factor for realizing economical competitive fusion reactors. The results show that with the conventional TF coil maximum field (12T), physics progress in β-value (or Troyon coefficient) has the most considerable effect on the reduction of fusion plant COE (Cost of Electricity) while the achievement of H factor = 2-3 and neutron wall load =∼5MW/m 2 is necessary. The results also show that with the improvement of TF coil maximum field, reactors with a high aspect ratio are economically advantageous because of low plasma current driving power while the improvement of current density in the conductors and yield strength of support structures is indispensable. (author)

Trends in radiation protection: possible effects on fusion power plant design

International Nuclear Information System (INIS)

Eurajoki, Tapani; Frias, Manuel Pascual; Orlandi, Sergio

2003-01-01

Since the design of fusion power plants involves long-term issues, ranging over several decades, it is useful to try to foresee under what kind of regulations the first fusion plants are to be operated. Application of present radiological regulations and practice to a fusion power plant concept is considered. The current design phase of fusion power plants motivates the top-down dose assessment, but it is crucial to aim at bottom-up assessments to ensure radiation doses as low as reasonably achievable. Since several issues, relating both to our knowledge on radiation as well as to the practice of radiation protection, may change in the future, it is necessary to continuously follow the development in the further design of fusion power plants

Issues in the commercialization of magnetic fusion power

International Nuclear Information System (INIS)

Rockwood, A.D.; Willke, T.L.

1979-12-01

This study identifies and outlines the issues that must be considered if fusion is to be put into commercial practice. The issues are put into perspective around a consistent framework and a program of study and research is recommended to anticipate and handle the issues for a successful fusion commercialization program

From patronage to partnership: Toward a new industrial policy for the fusion program

International Nuclear Information System (INIS)

Miller, B.

1992-01-01

The genesis of the overall assessment can be found in a February 1992 letter to the Department's Director of Research from the Fusion Energy Advisory Committee (FEAC) which suggested that the current level of industrial involvement in the fusion program is less than that needed to keep it actively involved for the long term. Specifically, FEAC recommended that open-quotes[in order] to provide U.S. industry with knowledge of fusion requirements and to secure the maximum benefit from industrial involvement, DOE should develop a plan that deliberately includes a broader and more integral industrial participation in the fusion program.close quotes This is another way of expressing the generally felt concern that after 30 years of waiting for some signal of a national commitment to the program, industry interest in it is flagging. Consider the following evidence. There is not significant investor-owner or public utility interest in the program at this time. The Electric Power Research Institute (EPRI), which once was committed to the idea of fusion as the long-term solution to our energy needs, now sees it playing no part in meeting the nation's long-term electrical energy demand. In its most recent annual report, it makes no mention of fusion as a future utility option, effectively consigning it to the role of perennial bridesmaid. Things are little better on the vendor side of industry that has provided the bulk of all industrial involvement in the program. In the final analysis they are profit making entities and must pay attention to the bottom-line of even their speculative research and development efforts or eventually abandon them. In short, there is no operative government policy on industrial involvement in the fusion program, only an unwritten guideline that industry growth will follow growth in the laboratory or core programs in good times and industry contraction will precede core contraction in bad times

Experimental fusion power reactor conceptual design study. Final report. Volume II

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following sections: (1) reactor components, (2) auxiliary systems, (3) operations, (4) facility design, (5) program considerations, and (6) conclusions and recommendations

Fusion programs in Applied Plasma Physics

International Nuclear Information System (INIS)

1992-07-01

The Applied Plasma Physics (APP) program at General Atomics (GA) described here includes four major elements: (a) Applied Plasma Physics Theory Program, (b) Alpha Particle Diagnostic, (c) Edge and Current Density Diagnostic, and (d) Fusion User Service Center (USC). The objective of the APP theoretical plasma physics research at GA is to support the DIII-D and other tokamak experiments and to significantly advance our ability to design a commercially-attractive fusion reactor. We categorize our efforts in three areas: magnetohydrodynamic (MHD) equilibria and stability; plasma transport with emphasis on H-mode, divertor, and boundary physics; and radio frequency (rf). The objective of the APP alpha particle diagnostic is to develop diagnostics of fast confined alpha particles using the interactions with the ablation cloud surrounding injected pellets and to develop diagnostic systems for reacting and ignited plasmas. The objective of the APP edge and current density diagnostic is to first develop a lithium beam diagnostic system for edge fluctuation studies on the Texas Experimental Tokamak (TEXT). The objective of the Fusion USC is to continue to provide maintenance and programming support to computer users in the GA fusion community. The detailed progress of each separate program covered in this report period is described in the following sections

Safety issues relating to the design of fusion power facilities

International Nuclear Information System (INIS)

Stasko, R.R.; Wong, K.Y.; Russell, S.B.

1986-06-01

In order to make fusion power a viable future source of energy, it will be necessary to ensure that the cost of power for fusion electric generation is competitive with advanced fission concepts. In addition, fusion power will have to live up to its original promise of being a more radiologically benign technology than fission, and be able to demonstrate excellent operational safety performance. These two requirements are interrelated, since the selection of an appropriate safety philosophy early in the design phase could greatly reduce or eliminate the capital costs of elaborate safety related and protective sytems. This paper will briefly overview a few of the key safety issues presently recognized as critical to the ultimate achievement of licensable, environmentally safe and socially acceptable fusion power facilities. 12 refs

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

Issues in the commercialization of magnetic fusion power

Energy Technology Data Exchange (ETDEWEB)

Rockwood, A.D.; Willke, T.L.

1979-12-01

This study identifies and outlines the issues that must be considered if fusion is to be put into commercial practice. The issues are put into perspective around a consistent framework and a program of study and research is recommended to anticipate and handle the issues for a successful fusion commercialization program. (MOW)

Optimization of nonthermal fusion power consistent with energy channeling

International Nuclear Information System (INIS)

Snyder, P.B.; Herrmann, M.C.; Fisch, N.J.

1995-02-01

If the energy of charged fusion products can be diverted directly to fuel ions, non-Maxwellian fuel ion distributions and temperature differences between species will result. To determine the importance of these nonthermal effects, the fusion power density is optimized at constant-β for nonthermal distributions that are self-consistently maintained by channeling of energy from charged fusion products. For D-T and D- 3 He reactors, with 75% of charged fusion product power diverted to fuel ions, temperature differences between electrons and ions increase the reactivity by 40-70%, while non- Maxwellian fuel ion distributions and temperature differences between ionic species increase the reactivity by an additional 3-15%

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

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,...

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

Fusion power from lunar resources

International Nuclear Information System (INIS)

Kulcinski, G.L.; Schmitt, H.H.

1992-01-01

This paper reports that the moon contains an enormous energy source in 3 He deposited by the solar wind. Fusion of only 100 kg of 3 He with deuterium in thermonuclear fusion power plants can produce > 1000 MW (electric) of electrical energy, and the lunar resource base is estimated at 1 x 10 9 kg of 3 He. This fuel can supply >1000 yr of terrestrial electrical energy demand. The methods for extracting this fuel and the other solar wind volatiles are described. Alternate uses of D- 3 He fusion in direct thrust rockets will enable more ambitious deep-space missions to be conducted. The capability of extracting hydrogen, water, nitrogen, and other carbon-containing molecules will open up the moon to a much greater level of human settlement than previously thought

Complexity and availability for fusion power plants: The potential advantages of inertial fusion energy

International Nuclear Information System (INIS)

Perkins, L.J.

1997-01-01

Probably the single largest advantage of the inertial route to fusion energy (IFE) is the perception that its power plant embodiments could achieve acceptable capacity factors. This is a result of its relative simplicity, the decoupling of the driver and reactor chamber, and the potential to employ thick liquid walls. The author examines these issues in terms of the complexity, reliability, maintainability and, therefore, availability of both magnetic and inertial fusion power plants and compares these factors with corresponding scheduled and unscheduled outage data from present day fission experience. The author stresses that, given the simple nature of a fission core, the vast majority of unplanned outages in fission plants are due to failures outside the reactor vessel itself. Given one must be prepared for similar outages in the analogous plant external to a fusion power core, this puts severe demands on the reliability required of the fusion core itself. The author indicates that such requirements can probably be met for IFE plants. He recommends that this advantage be promoted by performing a quantitative reliability and availability study for a representative IFE power plant and suggests that databases are probably adequate for this task. 40 refs., 4 figs., 3 tabs

Towards upper power levels: thermonuclear fusion

International Nuclear Information System (INIS)

Vedel, Jean

1983-01-01

This paper is a brief introduction to the use of power lasers to achieve controlled thermonuclear fusion. After shortly describing thermonuclear fusion and the conditions of temperature, density and duration required it is showed how the laser enables such conditions to be created. The neodymium-doped glass laser NOVA that is being installed at the Livermore laboratory in the USA is described; at the time of its completion in 1984, this laser will be the most powerful in the world. In comparison, the OCTAL laser in operation at the Limeil establishment ''Centre d'Etudes'' of ''Commissariat Francais a l'Energie Atomique'' (the French atomic energy authority) is more modest; it is presented here [fr

Pulsed power accelerators for particle beam fusion

International Nuclear Information System (INIS)

Martin, T.H.; Barr, G.W.; VanDevender, J.P.; White, R.A.; Johnson, D.L.

1980-01-01

Sandia National Laboratories is completing the construction phase of the Particle Beam Fusion Accelerator-I (PBFA-I). Testing of the 36 module, 30 TW, 1 MJ output accelerator is in the initial stages. The 4 MJ, PBFA Marx generator has provided 3.6 MA into water-copper sulfate load resistors with a spread from first to last Marx firing between 15 to 25 ns and an output power of 5.7 TW. This accelerator is a modular, lower voltage, pulsed power device that is capable of scaling to power levels exceeding 100 TW. The elements of the PBFA technology and their integration into an accelerator system for particle beam fusion will be discussed

Evaluation of the energy required for constructing and operating a fusion power plant

International Nuclear Information System (INIS)

Buende, R.

1982-09-01

The energy required for constructing and operating a tokamak fusion power plant is appraised with respect to the energy output during the lifetime of the plant. A harvesting factor is deduced as a relevant figure of energetic merit and is used for a comparison between fusion, fission, and coal-fired power plants. Because fusion power plants involve considerable uncertainties the comparison is supplemented by a sensitivity analysis. In comparison with Light Water Reactor plants fusion power plants appear to be rather favourable in this respect. The energy required for providing the fuel is relatively low for fusion plants, thus overcompensating the considerable higher amount of energy necessary for constructing the fusion power plant. (orig.)

Magnetic fusion reactor economics

International Nuclear Information System (INIS)

Krakowski, R.A.

1995-01-01

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

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

Review of the Fusion Theory and Computing Program. Fusion Energy Sciences Advisory Committee (FESAC)

International Nuclear Information System (INIS)

Antonsen, Thomas M.; Berry, Lee A.; Brown, Michael R.; Dahlburg, Jill P.; Davidson, Ronald C.; Greenwald, Martin; Hegna, Chris C.; McCurdy, William; Newman, David E.; Pellegrini, Claudio; Phillips, Cynthia K.; Post, Douglass E.; Rosenbluth, Marshall N.; Sheffield, John; Simonen, Thomas C.; Van Dam, James

2001-01-01

At the November 14-15, 2000, meeting of the Fusion Energy Sciences Advisory Committee, a Panel was set up to address questions about the Theory and Computing program, posed in a charge from the Office of Fusion Energy Sciences (see Appendix A). This area was of theory and computing/simulations had been considered in the FESAC Knoxville meeting of 1999 and in the deliberations of the Integrated Program Planning Activity (IPPA) in 2000. A National Research Council committee provided a detailed review of the scientific quality of the fusion energy sciences program, including theory and computing, in 2000.

The heavy ion fusion research program in West Germany

International Nuclear Information System (INIS)

Bock, R.

1984-01-01

The study on the feasibility of heavy ion beam for inertial confinement fusion was started four years ago, setting the main goal to identify and investigate the key issues of heavy ion fusion concept. The fund for this program has been provided by the Federal Ministry of Research and Technology. In this paper, the outline of the present research is shown, and some recent achievement is summarized. Moreover, the idea about the goal and the new direction of the future program are discussed. In the present program, two activities are distinguished, that is, the expermental and theoretical studies on accelerators, target physics and atomic physics, and the conceptual design study for a heavy ion-driven power plant. A RF linac with storage rings was chosen as the driver concept. In the accelerator research, ion source studies, RFQ development and beam transport measurement have been considered. Two beam transport experiments were carried out. In the conceptual design study, the HIBALL driver concept, the reactor chamber having the first wall protection using Pb-Li eutectic and so on have been studied. An accelerator facility of modest size has been suggested for basic accelerator physics studies. (Kako, I.)

Magnetic Fusion Science Fellowship program: Summary of program activities for calendar year 1986

International Nuclear Information System (INIS)

1986-01-01

This report describes the 1985-1986 progress of the Magnetic Fusion Science Fellowship program (MFSF). The program was established in January of 1985 by the Office of Fusion Energy (OFE) of the US Department of Energy (DOE) to encourage talented undergraduate and first-year graduate students to enter qualified graduate programs in the sciences related to fusion energy development. The program currently has twelve fellows in participating programs. Six new fellows are being appointed during each of the program's next two award cycles. Appointments are for one year and are renewable for two additional years with a three year maximum. The stipend level also continues at a $1000 a month or $12,000 a year. The program pays all tuition and fee expenses for the fellows. Another important aspect of the fellowship program is the practicum. During the practicum fellows receive three month appointments to work at DOE designated fusion science research and development centers. The practicum allows the MFSF fellows to directly participate in on-going DOE research and development programs

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

Controlled thermonuclear fusion power apparatus and method

International Nuclear Information System (INIS)

Bussard, R.W.; Coppi, B.

1982-01-01

This invention provides a modular fusion reactor system containing several fusion power cores, each of relatively small size and low cost. Energy from the cores is absorbed in the core structure and within a surrounding blanket, and the cores themselves may be individually removed from the blanket and replaced as they deteriorate from high radiation flux damage

Introduction to Nuclear Fusion Power and the Design of Fusion Reactors. An Issue-Oriented Module.

Science.gov (United States)

Fillo, J. A.

This three-part module focuses on the principles of nuclear fusion and on the likely nature and components of a controlled-fusion power reactor. The physical conditions for a net energy release from fusion and two approaches (magnetic and inertial confinement) which are being developed to achieve this goal are described. Safety issues associated…

Fusion power, who needs it?

International Nuclear Information System (INIS)

Kaw, P.K.

1993-01-01

It is pointed out that the fusion community world wide has not aggressively pursued a faster pace of development, which can indeed be justified on the basis of its technical accomplishments, because of certain faulty assumptions. Taking some relevant data of energy consumption (based on fossil fuels) and its environmental impact in the projections for developing countries like India and China, it is demonstrated that there is extreme urgency (time-scale of less than 20-25 years) to develop technologies like fusion if one has to prevent stagnation of per capita energy production (and quality of life) in these countries. We conclude by calling for a new aggressive goal for the world wide fusion programme, namely development of a demonstration power plant producing electricity in an environmentally acceptable manner by the year 2015. (author). 6 refs., 5 tabs., 2 figs

Fast-imploding-linear fusion power

International Nuclear Information System (INIS)

Moses, R.W.; Krakowski, R.A.; MIller, R.L.

1978-01-01

A Fast-Liner Reactor (FLR) conceptual design is summarized. The FLR is a pulsed D-T fusion concept that envisages the implosion of a small, cylindrical (0.2-m radius, 0.2-m length), metallic shell onto an initially warm plasma to achieve net energy production by means of rapid but adiabatic compression to thermonuclear temperature. The primary purpose of this study is to examine by means of detailed computer models the physical processes and constraints which may limit this unique approach to high-density fusion power. On the basis of an optimized physics operating point, a conceptual reactor embodiment is described

Compact approach to fusion power reactors

International Nuclear Information System (INIS)

Hagenson, R.L.; Krakowski, R.A.; Bathke, C.G.; Miller, R.L.

1984-01-01

The potential of the Reversed-Field Pinch (RFP) for development into an efficient, compact, copper-coil fusion reactor has been quantified by comprehensive parametric tradeoff studies. These compact systems promise to be competitive in size, power density, and cost to alternative energy sources. Conceptual engineering designs that largely substantiate these promising results have since been completed. This 1000-MWe(net) design is described along with a detailed rationale and physics/technology assessment for the compact approach to fusion

Local wall power loading variations in thermonuclear fusion devices

International Nuclear Information System (INIS)

Carroll, M.C.; Miley, G.H.

1989-01-01

A 2 1/2-dimensional geometric model is presented that allows calculation of power loadings at various points on the first wall of a thermonuclear fusion device. Given average wall power loadings for brems-strahlung, cyclotron radiation charged particles, and neutrons, which are determined from various plasma-physics computation models, local wall heat loads are calculated by partitioning the plasma volume and surface into cells and superimposing the heating effects of the individual cells on selected first-wall differential areas. Heat loads from the entire plasma are thus determined as a function of position on the first-wall surface. Significant differences in local power loadings were found for most fusion designs, and it was therefore concluded that the effect of local power loading variations must be taken into account when calculating temperatures and heat transfer rates in fusion device first walls

Design study of electrical power supply system for tokamak fusion power reactor

International Nuclear Information System (INIS)

1977-01-01

Design study of the electrical power supply system for a 2000MWt Tokamak-type fusion reactor has been carried out. The purposes are to reveal and study problems in the system, leading to a plan of the research and development. Performed were study of the electrical power supply system and design of superconducting inductive energy storages and power switches. In study of the system, specification and capability of various power supplies for the fusion power reactor and design of the total system with its components were investigated. For the superconducting inductive energy storages, material choice, design calculation, and structural design were conducted, giving the size, weight and performance. For thyristor switches, circuit design in the parallel / series connection of element valves and cooling design were studied, providing the size and weight. (auth.)

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

Development of D+3He Fusion Electric Thrusters and Power Supplies for Space

Science.gov (United States)

Morse, Thomas M.

1994-07-01

Development of D+3He Fusion Electric Thrusters (FET) and Power Supplies (FPS) should occur at a lunar base because of the following: availability of helium-3, a vacuum better than on Earth, low K in shade reachable by radiant cooling, supply of ``high temp'' superconducting ceramic-metals, and a low G environment. The early FET will be much smaller than an Apollo engine, with specific impulse of 10,000-100,000-s. Solar power and low G will aid early development. To counter the effect of low G on humans, centrifuges will be employed for sleeping and resting. Work will be done by telerobotic view control. The FPS will be of comparable size, and will generate power mainly by having replaceable rectennas, resonant to the fusion synchrotron radiation. FPSs are used for house keeping power and initiating superconduction. Spaceships will carry up to ten FETs and two FPSs. In addition to fusion fuel, the FET will inject H or Li low mass propellant into the fusion chamber. Developing an FET would be difficult on Earth. FET spaceships will park between missions in L1, and an FET Bus will fetch humans/supplies from Moon and Earth. Someday FETs, with rocket assist, will lift spaceships from Earth, and make space travel to planets far cheaper, faster, and safer, than at present. Too long a delay due to the space station, or the huge cost of getting into space by current means, will damage the morale of the space program.

Study of Heating and Fusion Power Production in ITER Discharges

International Nuclear Information System (INIS)

Rafiq, T.; Kritz, A. H.; Bateman, G.; Kessel, C.; McCune, D. C.; Budny, R. V.; Pankin, A. Y.

2011-01-01

ITER simulations, in which the temperatures, toroidal angular frequency and currents are evolved, are carried out using the PTRANSP code starting with initial profiles and boundary conditions obtained from TSC code studies. The dependence of heat deposition and current drive on ICRF frequency, number of poloidal modes, beam orientation, number of Monte Carlo particles and ECRH launch angles is studied in order to examine various possibilities and contingencies for ITER steady state and hybrid discharges. For the hybrid discharges, the fusion power production and fusion Q, computed using the Multi-Mode MMM v7.1 anomalous transport model, are compared with those predicted using the GLF23 model. The simulations of the hybrid scenario indicate that the fusion power production at 1000 sec will be approximately 500 MW corresponding to a fusion Q = 10.0. The discharge scenarios simulated aid in understanding the conditions for optimizing fusion power production and in examining measures of plasma performance.

Fusion Energy Sciences Program at LANL

Energy Technology Data Exchange (ETDEWEB)

Leeper, Ramon J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-15

This presentation provides a strategic plan and description of investment areas; LANL vision for existing programs; FES portfolio and other specifics related to the Fusion Energy Sciences program at LANL.

The path from ITER to a power plant - initial results from the ARIES ''Pathways'' program

International Nuclear Information System (INIS)

Najmabadi, F.

2007-01-01

The US national power plant studies program, ARIES, has initiated a 3-year integrated study, called the ''Pathways Program'' to investigate what the fusion program needs to do, in addition to successful operation of the ITER, in order to transform fusion into a commercial reality. The US power industry and regulatory agencies view the demonstration power plant, DEMO, as a device which is build and operated by industry, possibly with government participation, to demonstrate the commercial readiness of fusion power. As such, the ''Pathways'' programs will investigate what is needed, in addition to successful operation of ITER, to convince industry to move forward with a fusion DEMO. While many reports exists that provide a strategic view of the needs for fusion development; in the ITER era, a much more detailed view is needed to provide the necessary information for program planning. By comparing the anticipated results from ITER and existing facilities with the requirements for a power plant in the first phase of the Pathways study, we will develop a comprehensive list of remaining R and D items for developing fusion, will identify metrics for distributing resources among R and D issues, and will identify which of those items can/should be done in existing or simulation facilities. In the second phase of the study, we will develop potential embodiments for the fusion test facility (ies) and explore their cost/performance parametrically. An important by-product of this study is the identification of key R and D issues that can be performed and resolved in existing facilities to make the fusion facility cheaper and/or a higher performance device. This paper summarizes the results from the first phase of our study. We have adopted a ''holistic'' or integrated approach with the focus on the needs of the customer. In such an approach, the remaining R and D should generate all of the information needed by industry to move forward with the DEMO, i.e., data needed to

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

Potential environmental effects of fusion reactor power plants

International Nuclear Information System (INIS)

Young, J.R.; Gore, B.F.; Coffman, F.E.

1976-01-01

Construction and operation of fusion power plants is expected to reduce the total environmental effects of 21st century power generation. Fusion power plant impacts due to noise, odors, vibrations, and sanitary wastes are expected to be insignificant. impacts due to land use, chemical releases, and aesthetics are expected to be reduced. Impacts due to heat releases, local socio-economic changes, and non-radioactive liquid and solid disposal are expected to be comparable to those for the alternative fission or coal-fired power systems. Radiation doses to the public due to radioactive wastes are expected to be comparable to, or less than, the trivial low doses due to fission power systems. Research and development will be required, however, to assure adequate containment of tritium, the primary radioisotope of concern. Prevention of accidental tritium releases is within the capability of current engineering practice. Current technology is capable of handling the solid radioactive waste which may be produced, with insignificant environmental impact. Major research efforts are necessary to determine if subtle long-term effects of magnetic fields exist and should be of concern. In view of the large quantities of construction materials required for fusion. Material availability may dictate 21st century power plant design and construction. The accident potential of fusion power plants should be lower than for fission systems. Accidental criticalities and plasma runaways are not considered to be possible. Loss of coolant accidents are not expected to result in damage to the containment. No fission products or actinides are present to be released in an accident, and most activation products are immobilized in structures. The biological hazard of tritium is orders of magnitude smaller than for fission products and actinides. Safeguards against diversion of fissile materials are not expected to be necessary

Pulsed-power-supply development for fusion applications: special research support agreement

International Nuclear Information System (INIS)

1980-01-01

This is a final summary describing research and development work carried out by the Center for Electromechanics at The University of Texas at Austin (CEM-UT) for the Department of Energy during calendar years 1978, 1979, and 1980. The general purpose of this special research support program was to conduct research on pulsed power supply development for fusion applications in the areas of homopolar generators (HPGs), tokamak ohmic heating stuides, switching, and pulse compression technology

Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs

International Nuclear Information System (INIS)

1980-08-01

A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described

Fusion power demonstration - a baseline for the mirror engineering test reactor

International Nuclear Information System (INIS)

Henning, C.D.; Logan, B.G.; Neef, W.S.

1983-01-01

Developing a definition of an engineering test reactor (ETR) is a current goal of the Office of Fusion Energy (OFE). As a baseline for the mirror ETR, the Fusion Power Demonstration (FPD) concept has been pursued at Lawrence Livermore National Laboratory (LLNL) in cooperation with Grumman Aerospace, TRW, and the Idaho National Engineering Laboratory. Envisioned as an intermediate step to fusion power applications, the FPD would achieve DT ignition in the central cell, after which blankets and power conversion would be added to produce net power. To achieve ignition, a minimum central cell length of 67.5 m is needed to supply the ion and alpha particles radial drift pumping losses in the transition region. The resulting fusion power is 360 MW. Low electron-cyclotron heating power of 12 MW, ion-cyclotron heating of 2.5 MW, and a sloshing ion beam power of 1.0 MW result in a net plasma Q of 22. A primary technological challenge is the 24-T, 45-cm bore choke coil, comprising a copper hybrid insert within a 15 to 18 T superconducting coil

Report of the Integrated Program Planning Activity for the DOE Fusion Energy Sciences Program

International Nuclear Information System (INIS)

None

2000-01-01

This report of the Integrated Program Planning Activity (IPPA) has been prepared in response to a recommendation by the Secretary of Energy Advisory Board that, ''Given the complex nature of the fusion effort, an integrated program planning process is an absolute necessity.'' We, therefore, undertook this activity in order to integrate the various elements of the program, to improve communication and performance accountability across the program, and to show the inter-connectedness and inter-dependency of the diverse parts of the national fusion energy sciences program. This report is based on the September 1999 Fusion Energy Sciences Advisory Committee's (FESAC) report ''Priorities and Balance within the Fusion Energy Sciences Program''. In its December 5,2000, letter to the Director of the Office of Science, the FESAC has reaffirmed the validity of the September 1999 report and stated that the IPPA presents a framework and process to guide the achievement of the 5-year goals listed in the 1999 report. The National Research Council's (NRC) Fusion Assessment Committee draft final report ''An Assessment of the Department of Energy's Office of Fusion Energy Sciences Program'', reviewing the quality of the science in the program, was made available after the IPPA report had been completed. The IPPA report is, nevertheless, consistent with the recommendations in the NRC report. In addition to program goals and the related 5-year, 10-year, and 15-year objectives, this report elaborates on the scientific issues associated with each of these objectives. The report also makes clear the relationships among the various program elements, and cites these relationships as the reason why integrated program planning is essential. In particular, while focusing on the science conducted by the program, the report addresses the important balances between the science and energy goals of the program, between the MFE and IFE approaches, and between the domestic and international aspects

Fusion Simulation Program Execution Plan

International Nuclear Information System (INIS)

Brooks, Jeffrey

2011-01-01

. It will address the origins and structure of the plasma electric field, rotation, the L-H transition, and the wide variety of pedestal relaxation mechanisms. The Whole Device Model will predict the entire discharge evolution given external actuators (i.e., magnets, power supplies, heating, current drive and fueling systems) and control strategies. Based on components operating over a range of physics fidelity, the WDM will model the plasma equilibrium, plasma sources, profile evolution, linear stability and nonlinear evolution toward a disruption (but not the full disruption dynamics). The plan assumes that, as the FSP matures and demonstrates success, the program will evolve and grow, enabling additional science problems to be addressed. The next set of integration opportunities could include: 1) Simulation of disruption dynamics and their effects; 2) Prediction of core profile including 3D effects, mesoscale dynamics and integration with the edge plasma; 3) Computation of non-thermal particle distributions, self-consistent with fusion, radio frequency (RF) and neutral beam injection (NBI) sources, magnetohydrodynamics (MHD) and short-wavelength turbulence.

Safety and Environment aspects of Tokamak- type Fusion Power Reactor- An Overview

Science.gov (United States)

Doshi, Bharat; Reddy, D. Chenna

2017-04-01

Naturally occurring thermonuclear fusion reaction (of light atoms to form a heavier nucleus) in the sun and every star in the universe, releases incredible amounts of energy. Demonstrating the controlled and sustained reaction of deuterium-tritium plasma should enable the development of fusion as an energy source here on Earth. The promising fusion power reactors could be operated on the deuterium-tritium fuel cycle with fuel self-sufficiency. The potential impact of fusion power on the environment and the possible risks associated with operating large-scale fusion power plants is being studied by different countries. The results show that fusion can be a very safe and sustainable energy source. A fusion power plant possesses not only intrinsic advantages with respect to safety compared to other sources of energy, but also a negligible long term impact on the environment provided certain precautions are taken in its design. One of the important considerations is in the selection of low activation structural materials for reactor vessel. Selection of the materials for first wall and breeding blanket components is also important from safety issues. It is possible to fully benefit from the advantages of fusion energy if safety and environmental concerns are taken into account when considering the conceptual studies of a reactor design. The significant safety hazards are due to the tritium inventory and energetic neutron fluence induced activity in the reactor vessel, first wall components, blanket system etc. The potential of release of radioactivity under operational and accident conditions needs attention while designing the fusion reactor. Appropriate safety analysis for the quantification of the risk shall be done following different methods such as FFMEA (Functional Failure Modes and Effects Analysis) and HAZOP (Hazards and operability). Level of safety and safety classification such as nuclear safety and non-nuclear safety is very important for the FPR (Fusion

Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs

Energy Technology Data Exchange (ETDEWEB)

Davidson, Ronald C.

1980-08-01

A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described. (MOW)

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)

Fusion Safety Program Annual Report, Fiscal Year 1996

International Nuclear Information System (INIS)

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

1996-12-01

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

Design of power control system using SMES and SVC for fusion power plant

International Nuclear Information System (INIS)

Niiyama, K; Yagai, T; Tsuda, M; Hamajima, T

2008-01-01

A SMES (Superconducting Magnetic Energy Storage System) system with converter composed of self-commutated valve devices such as GTO and IGBT is available to control active and reactive power simultaneously. A SVC (Static Var Compensators) or STATCOM (Static Synchronous Compensator) is widely employed to reduce reactive power in power plants and substations. Owing to progress of power electronics technology using GTO and IGBT devices, power converters in the SMES system and the SVC can easily control power flow in few milliseconds. Moreover, since the valve devices for the SMES are equivalent to those for the SVC, the device cost must be reduced. In this paper the basic control system combined with the SMES and SVC is designed for large pulsed loads of a nuclear fusion power plant. This combined system largely expands the reactive power control region as well as the active one. The simulation results show that the combined system is effective and prospective for the nuclear fusion power plant

Electric power from laser fusion: the HYLIFE concept

International Nuclear Information System (INIS)

Monsler, M.; Blink, J.; Hovingh, J.; Meier, W.; Walker, P.; Maniscalco, J.

1978-06-01

A high yield lithium injection fusion energy chamber is described which can conceptually be operated with pulsed yields of several thousand megajoules a few times a second, using less than one percent of the gross thermal power to circulate the lithium. Because a one meter thick blanket of lithium protects the structure, no first wall replacement is envisioned for the life of the power plant. The induced radioactivity is reduced by an order of magnitude over solid blanket concepts. The design calls for the use of common ferritic steels and a power density approaching that of a LWR, promising shortened development times over other fusion concepts and reactor vessel costs comparable to a LMFBR

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

Accelerators for heavy ion inertial fusion: Progress and plans

International Nuclear Information System (INIS)

Bangerter, R.O.; Friedman, A.; Herrmannsfeldt, W.B.

1994-08-01

The Heavy Ion Inertial Fusion Program is the principal part of the Inertial Fusion Energy Program in the Office of Fusion Energy of the U.S. Department of Energy. The emphasis of the Heavy Ion Program is the development of accelerators for fusion power production. Target physics research and some elements of fusion chamber development are supported in the much larger Inertial Confinement Fusion Program, a dual purpose (defense and energy) program in the Defense Programs part of the Department of Energy. The accelerator research program will establish feasibility through a sequence of scaled experiments that will demonstrate key physics and engineering issues at low cost compared to other fusion programs. This paper discusses progress in the accelerator program and outlines how the planned research will address the key economic issues of inertial fusion energy

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

Canadian fusion fuels technology project

International Nuclear Information System (INIS)

1986-01-01

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

BNL heavy ion fusion program

International Nuclear Information System (INIS)

Maschke, A.W.

1978-01-01

A principal attraction of heavy ion fusion is that existing accelerator technology and theory are sufficiently advanced to allow one to commence the design of a machine capable of igniting thermonuclear explosions. There are, however, a number of features which are not found in existing accelerators built for other purposes. The main thrust of the BNL Heavy Ion Fusion program has been to explore these features. Longitudinal beam bunching, very low velocity acceleration, and space charge neutralization are briefly discussed

Neutron irradiation experiments for fusion reactor materials through JUPITER program

International Nuclear Information System (INIS)

Abe, K.; Namba, C.; Wiffen, F.W.; Jones, R.H.

1998-01-01

A Japan-USA program of irradiation experiments for fusion research, ''JUPITER'', has been established as a 6 year program from 1995 to 2000. The goal is to study ''the dynamic behavior of fusion reactor materials and their response to variable and complex irradiation environment''. This is phase-three of the collaborative program, which follows RTNS-II program (phase-1: 1982-1986) and FFTF/MOTA program (phase-2: 1987-1994). This program is to provide a scientific basis for application of materials performance data, generated by fission reactor experiments, to anticipated fusion environments. Following the systematic study on cumulative irradiation effects, done through FFTF/MOTA program. JUPITER is emphasizing the importance of dynamic irradiation effects on materials performance in fusion systems. The irradiation experiments in this program include low activation structural materials, functional ceramics and other innovative materials. The experimental data are analyzed by theoretical modeling and computer simulation to integrate the above effects. (orig.)

Fusion safety program annual report fiscal year 1997

International Nuclear Information System (INIS)

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

1998-01-01

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

Fusion safety program annual report fiscal year 1997

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-01

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

Conceptual design of inertial confinement fusion power plant

International Nuclear Information System (INIS)

Mima, Kunioki; Yamanaka, Tatsuhiko; Nakai, Sadao

1994-01-01

Presented is the status of the conceptual design studies of inertial confinement fusion reactors. The recent achievements of the laser fusion research enable us to refine the conceptual design of the power plant. In the paper, main features of several new conceptual designs of ICF reactor; KOYO, SIRIUS-P, HYLIFE-II and so on are summarized. In particular, the target design and the reactor chamber design are described. Finally, the overview of the laser fusion reactor and the irradiation system is also described. (author)

EBFA: pulsed power for fusion

International Nuclear Information System (INIS)

Martin, T.H.; VanDevender, J.P.; Barr, G.W.; Johnson, D.L.

1979-01-01

This paper will describe the EBFA I accelerator under construction for inertial confinement fusion studies with particle beams and will update previous publications concerning particle beam fusion accelerators. Previous information included Proto I, a triggered oil insulated 1 TW accelerator; Proto II, a water insulated 10 TW accelerator; and EBFA I, a 30 TW, 1 MJ accelerator. Some modifications to the original design have occurred. A new pulse-forming-line concept has been developed which increases the flexibility of the accelerator. The major problem of vacuum interface flashover has been solved by the use of long, magnetically-insulated, transmission lines. The first production module of EBFA I has been received, assembled, and is now undergoing extensive testing. The technology is extendable to at least a factor of ten above the projected EBFA capabilities of 30 TW and 1 MJ output. Progress on facilities associated with the Sandia Particle Beam fusion program is reported

THE GENERAL ATOMICS FUSION THEORY PROGRAM ANNUAL REPORT FOR FISCAL YEAR 2002

International Nuclear Information System (INIS)

PROJECT STAFF

2002-01-01

OAK B202 THE GENERAL ATOMICS FUSION THEORY PROGRAM ANNUAL REPORT FOR FISCAL YEAR 2002. The dual objective of the fusion theory program at General Atomics (GA) is to significantly advance the scientific understanding of the physics of fusion plasmas and to support the DIII-D and other tokamak experiments. The program plan is aimed at contributing significantly to the Fusion Energy Science and the Tokamak Concept Improvement goals of the Office of Fusion Energy Sciences (OFES)

Inertial confinement fusion (ICF)

International Nuclear Information System (INIS)

Nuckolls, J.

1977-01-01

The principal goal of the inertial confinement fusion program is the development of a practical fusion power plant in this century. Rapid progress has been made in the four major areas of ICF--targets, drivers, fusion experiments, and reactors. High gain targets have been designed. Laser, electron beam, and heavy ion accelerator drivers appear to be feasible. Record-breaking thermonuclear conditions have been experimentally achieved. Detailed diagnostics of laser implosions have confirmed predictions of the LASNEX computer program. Experimental facilities are being planned and constructed capable of igniting high gain fusion microexplosions in the mid 1980's. A low cost long lifetime reactor design has been developed

Fusion Safety Program annual report, fiscal year 1985

International Nuclear Information System (INIS)

Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

1987-02-01

The Fusion Safety Program (FSP) has supported magnetic fusion technology for seven years, and this is the seventh annual report issued by the FSP. Program focus is identification of the magnitude and distribution of radioactive inventories in fusion reactors, and research and analysis of postulated accident scenarios that could cause the release of a portion of these inventories. Research results are used to develop improved designs that can reduce the probability and magnitude of such releases and thus improve the overall safety of fusion reactors. During FY-1985, research activities continued and participation continued on the Ignition Systems Project (ISP). This report presents the significant results of EGandG Idaho, Inc., activities and those from outside contracts, and includes a list of publications produced during the year, and activities planned for FY-1986

Fusion Breeder Program interim report

International Nuclear Information System (INIS)

Moir, R.; Lee, J.D.; Neef, W.

1982-01-01

This interim report for the FY82 Fusion Breeder Program covers work performed during the scoping phase of the study, December, 1981-February 1982. The goals for the FY82 study are the identification and development of a reference blanket concept using the fission suppression concept and the definition of a development plan to further the fusion breeder application. The context of the study is the tandem mirror reactor, but emphasis is placed upon blanket engineering. A tokamak driver and blanket concept will be selected and studied in more detail during FY83

How much laser power can propagate through fusion plasma?

International Nuclear Information System (INIS)

Lushnikov, Pavel M; Rose, Harvey A

2006-01-01

Propagation of intense laser beams is crucial for inertial confinement fusion, which requires precise beam control to achieve the compression and heating necessary to ignite the fusion reaction. The National Ignition Facility (NIF), where fusion will be attempted, is now under construction. Control of intense beam propagation may be ruined by laser beam self-focusing. We have identified the maximum laser beam power that can propagate through fusion plasma without significant self-focusing and have found excellent agreement with recent experimental data. This maximum is determined by the collective forward stimulated Brillouin scattering instability which suggests a way to increase the maximum power by appropriate choice of plasma composition with implication for NIF designs. Our theory also leads to the prediction of anti-correlation between beam spray and backscatter and therefore raises the possibility of indirect control of backscatter through manipulation of plasma ionization state or acoustic damping. We find a simple expression for laser intensity at onset of enhanced beam angular divergence (beam spray)

Fundamental radiation effects studies in the fusion materials program

International Nuclear Information System (INIS)

Doran, D.G.

1982-01-01

Fundamental radiation effects studies in the US Fusion Materials Program generally fall under the aegis of the Damage Analysis and Fundamental Studies (DAFS) Program. In a narrow sense, the problem addressed by the DAFS program is the prediction of radiation effects in fusion devices using data obtained in non-representative environments. From the onset, the program has had near-term and long-term components. The premise for the latter is that there will be large economic penalties for uncertainties in predictive capability. Fusion devices are expected to be large and complex and unanticipated maintenance will be costly. It is important that predictions are based on a maximum of understanding and a minimum of empiricism. Gaining this understanding is the thrust of the long-term component. (orig.)

Fusion Reactor Safety Research Program annual report, FY-79

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1980-08-01

The objective of the program is the development, coordination, and execution of activities related to magnetic fusion devices and reactors that will: (a) identify and evaluate potential hazards, (b) assess and disclose potential environmental impacts, and (c) develop design standards and criteria that eliminate, mitigate, or reduce those hazards and impacts. The program will provide a sound basis for licensing fusion reactors. Included in this report are portions of four reports from two outside contractors, discussions of the several areas in which EG and G Idaho is conducting research activities, a discussion of proposed program plan development, mention of special tasks, a review of fusion technology program coordination by EG and G with other laboratories, and a brief view of proposed FY-80 activities

APEX and ALPS, high power density technology programs in the U.S

International Nuclear Information System (INIS)

Wong, C.P.C.; Berk, S.; Abdou, M.; Mattas, R.

1999-02-01

In fiscal year (FY) 1998 two new fusion technology programs were initiated in the US, with the goal of making marked progress in the scientific understanding of technologies and materials required to withstand high plasma heat flux and neutron wall loads. APEX is exploring new and revolutionary concepts that can provide the capability to extract heat efficiently from a system with high neutron and surface heat loads while satisfying all the fusion power technology requirements and achieving maximum reliability, maintainability, safety, and environmental acceptability. ALPS program is evaluating advanced concepts including liquid surface limiters and divertors on the basis of such factors as their compatibility with fusion plasma, high power density handling capabilities, engineering feasibility, lifetime, safety and R and D requirements. The APEX and ALPS are three-year programs to specify requirements and evaluate criteria for revolutionary approaches in first wall, blanket and high heat flux component applications. Conceptual design and analysis of candidate concepts are being performed with the goal of selecting the most promising first wall, blanket and high heat flux component designs that will provide the technical basis for the initiation of a significant R and D effort beginning in FY2001. These programs are also considering opportunities for international collaborations

Nuclear fusion power supply device

International Nuclear Information System (INIS)

Nakagawa, Satoshi.

1975-01-01

Object: To use a hybrid power supply device, which comprises a thyristor power supply and a diode power supply, to decrease cost of a nuclear fusion power supply device. Structure: The device comprises a thyristor power supply connected through a closing unit and a diode power supply connected in parallel through a breaker, input of each power supply being applied with an output voltage of a flywheel AC generator. When a current transformer is excited, a disconnecting switch is turned on to close the diode power supply and a current of the current transformer is increased by an automatic voltage regulator to a set value within a predetermined period of time. Next, the current is cut off by a breaker, and when the breaker is in on position, the disconnecting switch is opened to turn on the closing unit. Thus, when a plasma electric current reaches a predetermined value, the breaker is turned on, and the current of the current transformer is controlled by the thyristor power supply. (Kamimura, M.)

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

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

1993-01-01

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

PBFA [Particle Beam Fusion Accelerator] II: The pulsed power characterization phase

International Nuclear Information System (INIS)

Martin, T.H.; Turman, B.N.; Goldstein, S.A.

1987-01-01

The Particle Beam Fusion Accelerator II, PBFA II, is now the largest pulsed power device in operation. This paper summarizes its first year and a half of operation for the Department of Energy (DOE) Inertial Confinement Fusion (ICF) program. Thirty-six separate modules provide 72 output pulses that combine to form a 100 TW output pulse at the accelerator center. PBFA II was successfully test fired for the first time on December 11, 1985. This test completed the construction phase (Phase 1) within the expected schedule and budget. The accelerator checkout phase then started (Phase 2). The first priority during checkout was to bring the Phase 1 subsystems into full operation. The accelerator was first tested to determine overall system performance. Next, subsystems that were not performing adequately were modified. The accelerator is now being used for ion diode studies. 32 refs

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-01

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

Advanced concepts in the United States fusion program

International Nuclear Information System (INIS)

Dove, W.F.

1985-01-01

The goal of the magnetic fusion program is to establish the scientific and technological base for fusion energy. Development of a variety of magnetic confinement systems is essential to achieving that goal. The role of the advanced concepts program is to conduct experimental investigations of confinement concepts other than the tokamaks and tandem mirror concepts. The present advanced concepts program consists of the reversed-field-pinch (RFP), the spheromak and the field-reversed configuration (FRC). Significant new experiments in the RFP and FRC concepts have been approved and are described

Advanced materials: The key to attractive magnetic fusion power reactors

International Nuclear Information System (INIS)

Bloom, E.E.

1992-01-01

Fusion is one of the most attractive central station power sources from the viewpoint of potential safety and environmental impact characteristics. Studies also indicate that fusion can be economically competitive with other options such as fission reactors and fossil-fired power stations. However, to achieve this triad of characteristics we must develop advanced materials with properties tailored for performance in the various fusion reactor systems. This paper discusses the desired characteristics of materials and the status of materials technology in four critical areas: (1) structural material for the first wail and blanket (FWB), (2) plasma-facing materials, (3) materials for superconducting magnets, and (4) ceramics for electrical and structural applications

Advanced materials - the key to attractive magnetic fusion power reactors

International Nuclear Information System (INIS)

Bloom, E.E.

1992-01-01

Fusion is one of the most attractive central station power sources from the viewpoint of potential safety and environmental impact characteristics. Studies also indicate that fusion can be economically competitive with other options such as fission reactors and fossil-fired power stations. However, to achieve this triad of characteristics we must develop advanced materials with properties tailored for performance in the various fusion reactor systems. This paper discusses the desired characteristics of materials and the status of materials technology in four critical areas: (1) structural materials for the first wall and blanket (FWB), (2) plasmafacing materials, (3) materials for superconducting magnets, and (4) ceramics for electrical and structural applications. (author)

Commercial objectives, technology transfer, and systems analysis for fusion power development

Science.gov (United States)

Dean, Stephen O.

1988-09-01

Fusion is an inexhaustible source of energy that has the potential for economic commercial applications with excellent safety and environmental characteristics. The primary focus for the fusion energy development program is the generation of central station electricity. Fusion has the potential, however, for many other applications. The fact that a large fraction of the energy released in a DT fusion reaction is carried by high energy neutrons suggests potentially unique applications. In addition, fusion R and D will lead to new products and new markets. Each fusion application must meet certain standards of economic and safety and environmental attractiveness. For this reason, economics on the one hand, and safety and environment and licensing on the other, are the two primary criteria for setting long range commercial fusion objectives. A major function of systems analysis is to evaluate the potential of fusion against these objectives and to help guide the fusion R and D program toward practical applications. The transfer of fusion technology and skills from the national labs and universities to industry is the key to achieving the long range objective of commercial fusion applications.

LLL magnetic fusion research: the first 25 years

International Nuclear Information System (INIS)

Post, R.F.

1978-01-01

From its inception, the Laboratory has supported research directed at tapping controlled fusion. Our magnetic fusion energy program--now one of the major elements of the national fusion energy research effort--dates back to the Laboratory's founding in 1952. This article reviews the program's beginnings, progress, and present status in terms of its ultimate goal: to demonstrate a practical and economical means of generating power from controlled fusion reactions

Power-balance analysis of muon-catalyzed fusion-fission hybrid reactor systems

International Nuclear Information System (INIS)

Miller, R.L.; Krakowski, R.A.

1985-01-01

A power-balance model of a muon-catalyzed fusion system in the context of a fission-fuel factory is developed and exercised to predict the required physics performance of systems competitive with either pure muon-catalyzed fusion systems or thermonuclear fusion-fission fuel factory hybrid systems

Reaction-rate coefficients, high-energy ions slowing-down, and power balance in a tokamak fusion reactor plasma

International Nuclear Information System (INIS)

Tone, Tatsuzo

1978-07-01

Described are the reactivity coefficient of D-T fusion reaction, slowing-down processes of deuterons injected with high energy and 3.52 MeV alpha particles generated in D-T reaction, and the power balance in a Tokamak reactor plasma. Most of the results were obtained in the first preliminary design of JAERI Experimental Fusion Reactor (JXFR) driven with stationary neutral beam injection. A manual of numerical computation program ''BALTOK'' developed for the calculations is given in the appendix. (auth.)

Experimental fusion power reactor conceptual design study. Final report. Volume III

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following appendices: (1) tradeoff code analysis, (2) residual mode transport, (3) blanket/first wall design evaluations, (4) shielding design evaluation, (5) toroidal coil design evaluation, (6) E-coil design evaluation, (7) F-coil design evaluation, (8) plasma recycle system design evaluation, (9) primary coolant purification design evaluation, (10) power supply system design evaluation, (11) number of coolant loops, (12) power conversion system design evaluation, and (13) maintenance methods evaluation

Japanese program of materials research for fusion reactors

International Nuclear Information System (INIS)

Hasiguti, R.R.

1982-01-01

The Japanese program of materials research for fusion reactors is described based on the report to the Nuclear Fusion Council, the project research program of the Ministry of Education, Science and Culture, and other official documents. The alloy development for the first wall and its radiation damage are the main topics discussed in this paper. Materials viewpoints for the Japanese Tokamak facilities and the problems of irradiation facilities are also discussed. (orig.)

Purdue Contribution of Fusion Simulation Program

Energy Technology Data Exchange (ETDEWEB)

Jeffrey Brooks

2011-09-30

. It will address the origins and structure of the plasma electric field, rotation, the L-H transition, and the wide variety of pedestal relaxation mechanisms. The Whole Device Model will predict the entire discharge evolution given external actuators (i.e., magnets, power supplies, heating, current drive and fueling systems) and control strategies. Based on components operating over a range of physics fidelity, the WDM will model the plasma equilibrium, plasma sources, profile evolution, linear stability and nonlinear evolution toward a disruption (but not the full disruption dynamics). The plan assumes that, as the FSP matures and demonstrates success, the program will evolve and grow, enabling additional science problems to be addressed. The next set of integration opportunities could include: 1) Simulation of disruption dynamics and their effects; 2) Prediction of core profile including 3D effects, mesoscale dynamics and integration with the edge plasma; 3) Computation of non-thermal particle distributions, self-consistent with fusion, radio frequency (RF) and neutral beam injection (NBI) sources, magnetohydrodynamics (MHD) and short-wavelength turbulence.

Research Needs for Magnetic Fusion Energy Sciences

Energy Technology Data Exchange (ETDEWEB)

Neilson, Hutch

2009-07-01

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

Development of high power solid-state laser for inertial fusion energy driver

International Nuclear Information System (INIS)

Yoshida, K.; Yamanaka, M.; Nakatsuka, M.; Sasaki, T.; Nakai, S.

1997-01-01

The design study of the laser fusion power plant KOYO has been conducted as a joint program of universities, national laboratories, and industries in Japan and also with international collaborations. In the design of KOYO, the gain scaling of direct drive implosion with 0.35 μ m wavelength laser light is used. A driver of diode pumped solid state laser (DPSSL) generates 4 MJ/pulse with 12 Hz and the output pulses are switched to deliver the laser energy successively to four chambers, which operate with 3 Hz. The chamber wall is protected with thick liquid metal which flows down in a SiC woven tube. Following to the conceptual design study, the critical key issues which may affect the technical and economical feasibility of the commercial power plant KOYO have been examined. Research and development of some key technologies have been performed. As the results of the studies on KOYO, it is concluded that the technical and economical feasibility of laser fusion reactor is well in our scope to reach

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

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

1993-12-01

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

Report of the 1992 EPRI Fusion Panel

International Nuclear Information System (INIS)

Hirsch, R.L.; Culler, F.; Hingorani, N.G.; Taylor, J.J.; Schneider, T.R.; Spencer, D.F.

1992-01-01

Fusion is one of only a few very long-term (multi-century) options for the central station generation of electric power. As such, an informed awareness of the status of fusion development is important to the electric utilities and to EPRI. In its recent open-quotes National Energy Strategyclose quotes report, the U.S. Department of Energy states that it intends to carry out a goal-oriented fusion development strategy, with the aim of operating a demonstration plant by about 2025 and a commercial power plant by about 2040. Around the time the DOE was preparing this strategy, budget pressures caused them to narrow their civilian development program to the tokamak magnetic confinement concept. A significant research program on inertial confinement fusion is maintained primarily for defense purposes but with possible civilian application also. Many in the utility and engineering communities have raised questions about the suitability of both the tokamak and inertial confinement as commercial power sources, while recognizing their unquestioned pre-eminence in achieving fusion plasma conditions. These questions, coupled with a possible interest in becoming more involved in the development of fusion power, led EPRI senior management to establish a panel of senior executives to consider a wide range of conceivable fusion reactor opportunities. The purposes of the 1992 EPRI Fusion Study were as follows: 1. To evaluate a wide range of fusion concepts from a utility desirability standpoint. 2. To enhance EPRI's perspective in fusion. 3. To provide guidance to DOE on fusion concept characteristics important to utilities. 4. To provide a basis for re-establishing DOE-EPRI communication and cooperation in fusion

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

Recycling of copper used in fusion power plants

International Nuclear Information System (INIS)

Forty, C.B.A.; Butterworth, G.J.; Turner, A.D.; Junkison, A.J.

1997-04-01

One of the major safety and environmental advantages of fusion power is a limited waste management burden on future generations. In this connection, the ability to recycle end-of-service materials from fusion power plant is beneficial both in terms of the conservation of natural resources and the minimisation of the volumes of activated wastes. After 100 years, the residual activity of near-plasma copper components exceeds that permitted for free release or contact handling. The presence of silver as a common impurity in copper may exacerbate this problem, through generation of 108m Ag. Removal of the silver impurity in a separate refining step prior to use of the copper in a fusion plant obviates the problems associated with formation of 108m Ag. Two alternative desilveration processes have been demonstrated; one involving the segregation of silver as AgBr and the other the absorption of Ag + by ion exchange. The present study demonstrates that conventional electrorefining techniques can be adapted to recover used copper in a single refining stage, with sufficient decontamination to permit its reuse in fusion power plants or, with a second stage, unrestricted release. Shielding requirements for the processing of scrap copper in conventional hot cells indicate a decay storage period of 50-100 years. To maximise the cost of savings of reclamation over direct geological disposal, the activation products may be separated out and disposed of in a metallic form. A substantial reduction in the overall volume of active waste should thus be achievable, especially if supercompaction can be applied to the product. (Author)

Recycling of copper used in fusion power plants

International Nuclear Information System (INIS)

Butterworth, G.J.; Forty, C.B.A.

1998-01-01

One of the major safety and environmental advantages of fusion power is a limited waste management burden on future generations. In this connection, the ability to recycle end-of-service materials from fusion power plants is beneficial both in terms of the conservation of natural resources and the minimisation of the volume of activated wastes. After 100 years, the residual activity of near-plasma copper components exceeds that permitted for free release or contact handling. The presence of silver as a common impurity in copper may exacerbate this problem, through generation of 108m Ag. Removal of the silver impurity in a separate refining step prior to use of the copper in a fusion plant obviates the problems associated with formation of 108m Ag. Two alternative desilverisation processes have been demonstrated; one involving the segregation of silver as AgBr and the other the absorption of Ag + by ion exchange. The present study demonstrates that conventional electrorefining techniques can be adapted to recover used copper in a single refining stage, with sufficient decontamination to permit its reuse in fusion power plants or, with a second stage, unrestricted release. Shielding requirements for the processing of scrap copper in conventional hot cells indicate a decay storage period of 50-100 years. To maximise the cost savings of reclamation over direct geological disposal, the activation products may be separated out and disposed of in a metallic form. A substantial reduction in the overall volume of active waste should thus be achievable, especially if supercompaction can be applied to the product. (orig.)

Fusion: Energy for the future

International Nuclear Information System (INIS)

1991-05-01

Fusion, which occurs in the sun and the stars, is a process of transforming matter into energy. If we can harness the fusion process on Earth, it opens the way to assuring that future generations will not want for heat and electric power. The purpose of this booklet is to introduce the concept of fusion energy as a viable, environmentally sustainable energy source for the twenty-first century. The booklet presents the basic principles of fusion, the global research and development effort in fusion, and Canada's programs for fusion research and development

Fusion reactor nucleonics: status and needs

International Nuclear Information System (INIS)

Lee, J.D.; Engholm, B.A.; Dudziak, D.J.; Haight, R.C.

1980-01-01

The national fusion technology effort has made a good start at addressing the basic nucleonics issues, but only a start. No fundamental nucleonics issues are seen as insurmountable barriers to the development of commercial fusion power. To date the fusion nucleonics effort has relied almost exclusively on other programs for nuclear data and codes. But as we progress through and beyond ETF type design studies the fusion program will need to support a broad based nucleonics effort including code development, sensitivity studies, integral experiments, data acquisition etc. It is clear that nucleonics issues are extremely important to fusion development and that we have only scratched the surface

Nuclear Power Plants Fault Diagnosis Method Based on Data Fusion

International Nuclear Information System (INIS)

Xie Chunli; Liu Yongkuo; Xia Hong

2009-01-01

The data fusion is a method suit for complex system fault diagnosis such as nuclear power plants, which is multisource information processing technology. This paper uses data fusion information hierarchical thinking and divides nuclear power plants fault diagnosis into three levels. Data level adopts data mining method to handle data and reduction attributes. Feature level uses three parallel neural networks to deal with attributes of data level reduction and the outputs of three networks are as the basic probability assignment of Dempster-Shafer (D-S) evidence theory. The improved D-S evidence theory synthesizes the outputs of neural networks in decision level, which conquer the traditional D-S evidence theory limitation which can't dispose conflict information. The diagnosis method was tested using correlation data of literature. The test results indicate that the data fusion diagnosis system can diagnose nuclear power plants faults accurately and the method has application value. (authors)

THE GENERAL ATOMICS FUSION THEORY PROGRAM ANNUAL REPORT FOR GRANT YEAR 2004

International Nuclear Information System (INIS)

PROJECT STAFF

2004-01-01

The dual objective of the fusion theory program at General Atomics (GA) is to significantly advance our scientific understanding of the physics of fusion plasmas and to support the DIII-D and other tokamak experiments. The program plan is aimed at contributing significantly to the Fusion Energy Science and the Tokamak Concept Improvement goals of the Office of Fusion Energy Sciences (OFES)

Materials program for magnetic fusion energy

International Nuclear Information System (INIS)

Zwilsky, K.M.; Cohen, M.M.; Finfgeld, C.R.; Reuther, T.C.

1978-01-01

The Magnetic Fusion Reactor Materials Program is currently operating at a level of $7.8M. The program is divided into four technical areas which cover both short and long term problems. These are: Alloy Development for Irradiation Performance, Damage Analysis and Fundamental Studies, Plasma-Materials Interaction, and Special Purpose Materials. A description of the program planning process, the continuing management structure, and the resulting documents is presented

Design aspects of a multipurpose fusion power plant for desalination and agrochemical processes

International Nuclear Information System (INIS)

Sabri, Z.A.

1975-02-01

A description is given of the skeletal structure of a multipurpose fusion power plant, designed for desalination and agrochemicals production. The plant is a complex that comprises dual purpose power and desalination units, separation and processing units for recovery of soluble salts in the effluent of the desalination unit, mariculture units for production of algae for food and as food for shrimp and other fish species. The electrical power unit is a two-component fusion device that burns deuterium and helium-3 utilizing a fast fusion cycle

Repetitive pulsed power technology for inertial-confinement fusion

International Nuclear Information System (INIS)

Prestwich, K.R.; Buttram, M.T.

1983-01-01

The pulsed power requirements for inertial-confinement fusion reactors are defined for ion-beam and laser drivers. Several megajoule beams with 100's of terrawatt peak powers must be delivered to the reactor chamber 1 to 10 times per second. Ion-beam drivers are relatively efficient requiring less energy storage in the pulsed-power system but more time compression in the power flow chain than gas lasers. These high peak powers imply very large numbers of components for conventional pulse-power systems. A new design that significantly reduces the number of components is presented

Which are the competitors for a fusion power plant?

International Nuclear Information System (INIS)

Miller, Ronald L.

2000-01-01

The (future) competitive position of central-station fusion power will depend on the resolution of several broad public-policy issues, including the provision of adequate electrical energy to a growing world population and the interaction of economic and environmental considerations meeting evolving standards of public acceptance and regulatory compliance. Candidate baseload central-station power plants, fusion or other, will be expected to contend for preferential market penetration against an evolving set of performance indicators or metrics (e.g. cost of electricity) reflecting societal 'customer preferences' for abundant, affordable, safe, reliable, and environmentally benign sources. This competition is enhanced by transitions to price-deregulated regimes, overlaid by nuclear uncertainites and evolution beyond carbon-based fuels toward more renewables in the energy mix. From these top-level considerations, quantifiable attributes, including plant size (output), system power density, surface heat flux, recirculating power fraction, power-conversion efficiency, waste streams, and forced- and planned-outage rates emerge

Control of a laser inertial confinement fusion-fission power plant

Science.gov (United States)

Moses, Edward I.; Latkowski, Jeffery F.; Kramer, Kevin J.

2015-10-27

A laser inertial-confinement fusion-fission energy power plant is described. The fusion-fission hybrid system uses inertial confinement fusion to produce neutrons from a fusion reaction of deuterium and tritium. The fusion neutrons drive a sub-critical blanket of fissile or fertile fuel. A coolant circulated through the fuel extracts heat from the fuel that is used to generate electricity. The inertial confinement fusion reaction can be implemented using central hot spot or fast ignition fusion, and direct or indirect drive. The fusion neutrons result in ultra-deep burn-up of the fuel in the fission blanket, thus enabling the burning of nuclear waste. Fuels include depleted uranium, natural uranium, enriched uranium, spent nuclear fuel, thorium, and weapons grade plutonium. LIFE engines can meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the highly undesirable stockpiles of depleted uranium, spent nuclear fuel and excess weapons materials.

Nuclear engineering questions: power, reprocessing, waste, decontamination, fusion

International Nuclear Information System (INIS)

Walton, R.D. Jr.

1979-01-01

This volume contains papers presented at the chemical engineering symposium on nuclear questions. Specific questions addressed by the speakers included: nuclear power - why and how; commercial reprocessing - permanent death or resurrection; long-term management of commercial high-level wastes; long-term management of defense high-level waste; decontamination and decommissioning of nuclear facilities, engineering aspects of laser fusion I; and engineering aspects of laser fusion II. Individual papers have been input to the Energy Data Base previously

Wave heating and the U.S. magnetic fusion energy program

International Nuclear Information System (INIS)

Staten, H.S.

1985-01-01

The U.S. Government's support of the fusion program is predicated upon the long-term need for the fusion option in our energy future, as well as the near-term benefits associated with developments on the frontier of science and high technology. As a long-term energy option, magnetic fusion energy has the potential to provide an inexpensive, vast, and secure fuel reserve, to be environmentally clean and safe. It has many potential uses, which include production of central station electricity, fuel for fission reactors, synthetic fuels, and process heat for such applications as desalination of sea water. This paper presents an overview of the U.S. Government program for magnetic fusion energy. The goal and objectives of the U.S. program are reviewed followed by a summary of plasma experiments presently under way and the application of wave heating to these experiments

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

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

The ARIES-AT advanced tokamak, Advanced technology fusion power plant

International Nuclear Information System (INIS)

Najmabadi, Farrokh; Abdou, A.; Bromberg, L.

2006-01-01

The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive and competitive fusion power in order to guide fusion R and D. The 1000-MWe ARIES-AT design has a major radius of 5.2 m, a minor radius of 1.3 m, a toroidal β of 9.2% (β N = 5.4) and an on-axis field of 5.6 T. The plasma current is 13 MA and the current-drive power is 35 MW. The ARIES-AT design uses the same physics basis as ARIES-RS, a reversed-shear plasma. A distinct difference between ARIES-RS and ARIES-AT plasmas is the higher plasma elongation of ARIES-AT (κ x = 2.2) which is the result of a 'thinner' blanket leading to a large increase in plasma β to 9.2% (compared to 5% for ARIES-RS) with only a slightly higher β N . ARIES-AT blanket is a simple, low-pressure design consisting of SiC composite boxes with a SiC insert for flow distribution that does not carry any structural load. The breeding coolant (Pb-17Li) enters the fusion core from the bottom, and cools the first wall while traveling in the poloidal direction to the top of the blanket module. The coolant then returns through the blanket channel at a low speed and is superheated to ∼1100 deg. C. As most of the fusion power is deposited directly into the breeding coolant, this method leads to a high coolant outlet temperature while keeping the temperature of the SiC structure as well as interface between SiC structure and Pb-17Li to about 1000 deg. C. This blanket is well matched to an advanced Brayton power cycle, leading to an overall thermal efficiency of ∼59%. The very low afterheat in SiC composites results in exceptional safety and waste disposal characteristics. All of the fusion core components qualify for shallow land burial under U.S. regulations (furthermore, ∼90% of components qualify as Class-A waste, the lowest level). The ARIES

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

Laser-induced nuclear fusion

International Nuclear Information System (INIS)

Jablon, Claude

1977-01-01

Research programs on laser-induced thermonuclear fusion in the United States, in Europe and in USSR are reviewed. The principle of the fusion reactions induced is explained, together with the theoretical effects of the following phenomena: power and type of laser beams, shape and size of the solid target, shock waves, and laser-hydrodynamics coupling problems [fr

Electric power from near-term fusion reactors

International Nuclear Information System (INIS)

Longhurst, G.R.; Deis, G.A.; Miller, L.G.

1981-01-01

This paper examines requirements and possbilities of electric power production on near-term fusion reactors using low temperature cycle technology similar to that used in some geothermal power systems. Requirements include the need for a working fluid with suitable thermodynamics properties and which is free of oxygen and hydrogen to facilitate tritium management. Thermal storage will also be required due to the short system thermal time constants on near-time reactors. It is possbile to use the FED shield in a binary power cycle, and results are presented of thermodynamic analyses of this system

International program activities in magnetic fusion energy

International Nuclear Information System (INIS)

1986-03-01

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

Presentation Stations of the General Atomics Fusion Educational Program

Science.gov (United States)

Lee, R. L.; Fusion Group Education Outreach Team

1996-11-01

The General Atomics Fusion Group's Educational Program has been actively promoting fusion science and applications throughout San Diego County's secondary school systems for over three years. The educational program allows many students to learn more about nuclear fusion science, its applications, and what it takes to become an active participant in an important field of study. It also helps educators to better understand how to teach fusion science in their classroom. Tours of the DIII--D facility are a centerpiece of the program. Over 1000 students visited the DIII--D research facility during the 1995--1996 school year for a half-day of presentations, discussions, and hands-on learning. Interactive presentations are provided at six different stations by GA scientists and engineers to small groups of students during the tours. Stations include topics on energy, plasma science, the electromagnetic spectrum, radiation and risk assessment, and data acquisition. Included also is a tour of the DIII--D machine hall and model where students can see and discuss many aspects of the tokamak. Portions of each station will be presented and discussed.

Osiris and SOMBRERO inertial fusion power plant designs - summary, conclusions, and recommendations

International Nuclear Information System (INIS)

Meier, Wayne R.

1994-01-01

An 18 month study to evaluate the potential of inertial fusion energy (IFE) for electric power production has been completed. The primary objective of the study was to provide the US Department of Energy with an evaluation of the potential of inertial fusion for electric power production. The study included the conceptual design of two inertial fusion power plants. Osiris uses an induction linac heavy ion beam driver, and SOMBRERO uses a krypton fluoride laser driver. Conceptual designs were completed for the reactors, power conversion and plant facilities, and drivers. Environmental and safety aspects, technical issues, technology development needs, and economics of the final point designs were assessed and compared. This paper summarizes the results and conclusions of the conceptual designs and results of the assessment studies. We conclude that IFE has the potential of producing technically credible designs with environmental, safety, and economics characteristics that are just as attractive as magnetic fusion. Realizing this potential will require additional research and development on target physics, chamber design, target production and injection systems, and drivers. ((orig.))

Demonstration tokamak fusion power plant for early realization of net electric power generation

International Nuclear Information System (INIS)

Hiwatari, R.; Okano, K.; Asaoka, Y.; Shinya, K.; Ogawa, Y.

2005-01-01

A demonstration tokamak fusion power plant Demo-CREST is proposed as the device for early realization of net electric power generation by fusion energy. The plasma configuration for Demo-CREST is optimized to satisfy the electric breakeven condition (the condition for net electric power, P e net = 0 MW) with the plasma performance of the ITER reference operation mode. This optimization method is considered to be suitable for the design of a demonstration power plant for early realization of net electric power generation, because the demonstration power plant has to ensure the net electric generation. Plasma performance should also be more reliably achieved than in past design studies. For the plasma performance planned in the present ITER programme, net electric power from 0 to 500 MW is possible with Demo-CREST under the following engineering conditions: maximum magnetic field 16 T, thermal efficiency 30%, NBI system efficiency 50% and NBI current drive power restricted to 200 MW. By replacing the blanket system with one of higher thermal efficiency, a net electric power of about 1000 MW is also possible so that the performance of the commercial plant with Demo-CREST can also be studied from the economic point of view. The development path from the experimental reactor 'ITER' to the commercial plant 'CREST' through the demonstration power plant 'Demo-CREST' is proposed as an example of the fast track concept. (author)

Osiris and SOMBRERO inertial confinement fusion power plant designs

International Nuclear Information System (INIS)

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01

Conceptual designs and assessments have been completed for two inertial fusion energy (IFE) electric power plants. The detailed designs and results of the assessment studies are presented in this report. Osiris is a heavy-ion-beam (HIB) driven power plant and SOMBRERO is a Krypton-Fluoride (KrF) laser-driven power plant. Both plants are sized for a net electric power of 1000 MWe

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.)

FRESCO, a simplified code for cost analysis of fusion power plants

International Nuclear Information System (INIS)

Bustreo, C.; Casini, G.; Zollino, G.; Bolzonella, T.; Piovan, R.

2013-01-01

Highlights: • FRESCO is a code for rapid evaluation of the cost of electricity of a fusion power plant. • Parameters of the basic machine and unitary costs of components derived from ITER. • Power production components and plant power balance are extrapolated from PPCS. • A special effort is made in the investigation of the pulsed operation scenarios. • Technical and economical FRESCO results are compared with those of two PPCS models. -- Abstract: FRESCO (Fusion REactor Simplified COsts) is a code based on simplified models of physics, engineering and economical aspects of a TOKAMAK-like pulsed or steady-state fusion power plant. The experience coming from various aspects of ITER design, including selection of materials and operating scenarios, is exploited as much as possible. Energy production and plant power balance, including the recirculation requirements, are derived from two models of the PPCS European study, the helium cooled lithium/lead blanket model reactor (model AB) and the helium cooled ceramic one (model B). A detailed study of the availability of the power plant due, among others, to the replacement of plasma facing components, is also included in the code. The economics of the fusion power plant is evaluated through the levelized cost approach. Costs of the basic components are scaled from the corresponding values of the ITER project, the ARIES studies and SCAN model. The costs of plant auxiliaries, including those of the magnetic and electric systems, tritium plants, instrumentation, buildings and thermal energy storage if any, are recovered from ITER values and from those of other power plants. Finally, the PPCS models AB and B are simulated and the main results are reported in this paper

Scientific and Computational Challenges of the Fusion Simulation Program (FSP)

International Nuclear Information System (INIS)

Tang, William M.

2011-01-01

This paper highlights the scientific and computational challenges facing the Fusion Simulation Program (FSP) a major national initiative in the United States with the primary objective being to enable scientific discovery of important new plasma phenomena with associated understanding that emerges only upon integration. This requires developing a predictive integrated simulation capability for magnetically-confined fusion plasmas that are properly validated against experiments in regimes relevant for producing practical fusion energy. It is expected to provide a suite of advanced modeling tools for reliably predicting fusion device behavior with comprehensive and targeted science-based simulations of nonlinearly-coupled phenomena in the core plasma, edge plasma, and wall region on time and space scales required for fusion energy production. As such, it will strive to embody the most current theoretical and experimental understanding of magnetic fusion plasmas and to provide a living framework for the simulation of such plasmas as the associated physics understanding continues to advance over the next several decades. Substantive progress on answering the outstanding scientific questions in the field will drive the FSP toward its ultimate goal of developing the ability to predict the behavior of plasma discharges in toroidal magnetic fusion devices with high physics fidelity on all relevant time and space scales. From a computational perspective, this will demand computing resources in the petascale range and beyond together with the associated multi-core algorithmic formulation needed to address burning plasma issues relevant to ITER - a multibillion dollar collaborative experiment involving seven international partners representing over half the world's population. Even more powerful exascale platforms will be needed to meet the future challenges of designing a demonstration fusion reactor (DEMO). Analogous to other major applied physics modeling projects (e

Scientific and computational challenges of the fusion simulation program (FSP)

International Nuclear Information System (INIS)

Tang, William M.

2011-01-01

This paper highlights the scientific and computational challenges facing the Fusion Simulation Program (FSP) - a major national initiative in the United States with the primary objective being to enable scientific discovery of important new plasma phenomena with associated understanding that emerges only upon integration. This requires developing a predictive integrated simulation capability for magnetically-confined fusion plasmas that are properly validated against experiments in regimes relevant for producing practical fusion energy. It is expected to provide a suite of advanced modeling tools for reliably predicting fusion device behavior with comprehensive and targeted science-based simulations of nonlinearly-coupled phenomena in the core plasma, edge plasma, and wall region on time and space scales required for fusion energy production. As such, it will strive to embody the most current theoretical and experimental understanding of magnetic fusion plasmas and to provide a living framework for the simulation of such plasmas as the associated physics understanding continues to advance over the next several decades. Substantive progress on answering the outstanding scientific questions in the field will drive the FSP toward its ultimate goal of developing the ability to predict the behavior of plasma discharges in toroidal magnetic fusion devices with high physics fidelity on all relevant time and space scales. From a computational perspective, this will demand computing resources in the petascale range and beyond together with the associated multi-core algorithmic formulation needed to address burning plasma issues relevant to ITER - a multibillion dollar collaborative experiment involving seven international partners representing over half the world's population. Even more powerful exascale platforms will be needed to meet the future challenges of designing a demonstration fusion reactor (DEMO). Analogous to other major applied physics modeling projects (e

The role of radiation damage analysis in the fusion program

International Nuclear Information System (INIS)

Doran, D.G.

1983-01-01

The objective of radiation damage analysis is the prediction of the performance of facility components exposed to a radiation environment. The US Magnetic Fusion Energy materials program includes an explicit damage analysis activity within the Damage Analysis and Fundamental Studies (DAFS) Program. Many of the papers in these Proceedings report work done directly or indirectly in support of the DAFS program. The emphasis of this program is on developing procedures, based on an understanding of damage mechanisms, for applying data obtained in diverse radiation environments to the prediction of component behavior in fusion devices. It is assumed that the Fusion Materials Irradiation Test Facility will be available in the late 1980s to test (and calibrate where necessary) correlation procedures to the high fluences expected in commercial reactors. (orig.)

Regulatory aspects of fusion power-lessons from fission plants

International Nuclear Information System (INIS)

Natalizio, A.; Brunnader, H.; Sood, S.K.

1993-01-01

Experience from fission reactors has shown the regulatory process for licensing a nuclear facility to be legalistic, lengthy, unpredictable, and costly. This experience also indicates that much of the regulatory debate is focused on safety margins, that is, the smaller the safety margins the bigger the regulatory debate and the greater the amount of proof required to satisfy the regulatory. Such experience suggests that caution and prudence guide the development of a regulatory regime for fusion reactors. Fusion has intrinsic safety and environmental advantages over fission, which should alleviate significantly, or even eliminate, the regulatory problems associated with fission. The absence of a criticality concern and the absence of fission products preclude a Chernobyl type accident from occurring in a fusion reactor. Although in a fusion reactor there are large inventories of radioactive products that can be mobilized, the total quantity is orders of magnitude smaller than in fission power reactors. The bulk of the radioactivity in a fusion reactor is either activation products in steel structures, or tritium fuel supplies safely stored in the form of a metal tritide in storage beds. The quantity of tritium that can be mobilized under accident conditions is much less than ten million curies. This compares very favorably with a fission product inventory greater than ten billion curies in a fission power reactor. Furthermore, in a fission reactor, all of the reactivity is contained in a steel vessel that is pressurized to about 150 atmospheres, whereas in a fusion reactor, the inventory of radioactive material is dispersed in different areas of the plant, such that it is improbable that a single event could give rise to the release of the entire inventory to the environment. With such significant intrinsic safety advantages there is no a priori need to make fusion requirements/regulations more demanding and more stringent than fission

Fusion facility siting considerations

International Nuclear Information System (INIS)

Bussell, G.T.

1985-01-01

Inherent in the fusion program's transition from hydrogen devices to commercial power machines is a general increase in the size and scope of succeeding projects. This growth will lead to increased emphasis on safety, environmental impact, and the external effects of fusion in general, and of each new device in particular. A critically important consideration in this regard is site selection. The purpose of this paper is to examine major siting issues that may affect the economics, safety, and environmental impact of fusion

Structural materials requirements for in-vessel components of fusion power plants

International Nuclear Information System (INIS)

Schaaf, B. van der

2000-01-01

The economic production of fusion energy is determined by principal choices such as using magnetic plasma confinement or generating inertial fusion energy. The first generation power plants will use deuterium and tritium mixtures as fuel, producing large amounts of highly energetic neutrons resulting in radiation damage in materials. In the far future the advanced fuels, 3 He or 11 B, determine power plant designs with less radiation damage than in the first generation. The first generation power plants design must anticipate radiation damage. Solid sacrificing armour or liquid layers could limit component replacements costs to economic levels. There is more than radiation damage resistance to determine the successful application of structural materials. High endurance against cyclic loading is a prominent requirement, both for magnetic and inertial fusion energy power plants. For high efficiency and compactness of the plant, elevated temperature behaviour should be attractive. Safety and environmental requirements demand that materials have low activation potential and little toxic effects under both normal and accident conditions. The long-term contenders for fusion power plant components near the plasma are materials in the range from innovative steels, such as reduced activation ferritic martensitic steels, to highly advanced ceramic composites based on silicon carbide, and chromium alloys. The steels follow an evolutionary path to basic plant efficiencies. The competition on the energy market in the middle of the next century might necessitate the riskier but more rewarding development of SiCSiC composites or chromium alloys

Physics of laser fusion. Volume III. High-power pulsed lasers

International Nuclear Information System (INIS)

Holzrichter, J.F.; Eimerl, D.; George, E.V.; Trenholme, J.B.; Simmons, W.W.; Hunt, J.T.

1982-09-01

High-power pulsed lasers can deliver sufficient energy on inertial-confinement fusion (ICF) time scales (0.1 to 10 ns) to heat and compress deuterium-tritium fuel to fusion-reaction conditions. Several laser systems have been examined, including Nd:glass, CO 2 , KrF, and I 2 , for their ICF applicability. A great deal of developmental effort has been applied to the Nd:glass laser and the CO 2 gas laser systems; these systems now deliver > 10 4 J and 20 x 10 12 W to ICF targets. We are constructing the Nova Nd:glass laser at LLNL to provide > 100 kJ and > 100 x 10 12 W of 1-μm radiation for fusion experimentation in the mid-1980s. For ICF target gain > 100 times the laser input, we expect that the laser driver must deliver approx. 3 to 5 MJ of energy on a time scale of 10 to 20 ns. In this paper we review the technological status of fusion-laser systems and outline approaches to constructing high-power pulsed laser drivers

Advanced Fusion Reactors for Space Propulsion and Power Systems

Energy Technology Data Exchange (ETDEWEB)

Chapman, John J.

2011-06-15

In recent years the methodology proposed for conversion of light elements into energy via fusion has made steady progress. Scientific studies and engineering efforts in advanced fusion systems designs have introduced some new concepts with unique aspects including consideration of Aneutronic fuels. The plant parameters for harnessing aneutronic fusion appear more exigent than those required for the conventional fusion fuel cycle. However aneutronic fusion propulsion plants for Space deployment will ultimately offer the possibility of enhanced performance from nuclear gain as compared to existing ionic engines as well as providing a clean solution to Planetary Protection considerations and requirements. Proton triggered 11Boron fuel (p- 11B) will produce abundant ion kinetic energy for In-Space vectored thrust. Thus energetic alpha particles' exhaust momentum can be used directly to produce high Isp thrust and also offer possibility of power conversion into electricity. p-11B is an advanced fusion plant fuel with well understood reaction kinematics but will require some new conceptual thinking as to the most effective implementation.

Advanced Fusion Reactors for Space Propulsion and Power Systems

Science.gov (United States)

Chapman, John J.

2011-01-01

In recent years the methodology proposed for conversion of light elements into energy via fusion has made steady progress. Scientific studies and engineering efforts in advanced fusion systems designs have introduced some new concepts with unique aspects including consideration of Aneutronic fuels. The plant parameters for harnessing aneutronic fusion appear more exigent than those required for the conventional fusion fuel cycle. However aneutronic fusion propulsion plants for Space deployment will ultimately offer the possibility of enhanced performance from nuclear gain as compared to existing ionic engines as well as providing a clean solution to Planetary Protection considerations and requirements. Proton triggered 11Boron fuel (p- 11B) will produce abundant ion kinetic energy for In-Space vectored thrust. Thus energetic alpha particles "exhaust" momentum can be used directly to produce high ISP thrust and also offer possibility of power conversion into electricity. p- 11B is an advanced fusion plant fuel with well understood reaction kinematics but will require some new conceptual thinking as to the most effective implementation.

The fusion-FEM: 0,75 MW of mm-wave power

Energy Technology Data Exchange (ETDEWEB)

Smeets, P.H.M.; Bongers, W.A.; Brons, S.; Geer, C.A.J. van der; Lingier, K.L.; Manintveld, P.; Plomp, J.; Pluygers, J.; Poelman, A.J.; Sterk, A.B.; Verhoeven, A.G.A.; Urbanus, W.H. [FOM Inst. voor Plasmafysica ' Rijnhuizen' , Nieuwegein (Netherlands); Bratman, V.L.; Denisov, G.G.; Savilov, A.V. [Inst. of Applied Physics, Nizhny Novgorod (Russian Federation); Caplan, M. [Lawrence Livermore National Lab., CA (United States); Varfolomeev, A.A. [Russian Research Center ' Kurchatov Inst.' , Moscow (Russian Federation)

1998-07-01

The free-electron maser for fusion applications (Fusion-FEM) is the prototype for a high power, rapid tunable mm-wave source. The basic parameters such as frequency range (130 - 260 GHz) and output power (1 MW) are dedicated to Electron Cyclotron Resonance applications on future plasma fusion research devices, such as ITER. In October 1996 the electron beam was successfully accelerated and transported through the undulator and the mm-wave cavity. Loss currents are below 0.05 %. In October 1997 first lasing was achieved. The mm-wave output power has been measured at various frequencies and for various electron beam currents and energies. The highest output power reached so far is 730 kW at 205 GHz, for an electron beam of 7.2 A and 1.77 MeV. Both output power and start-up time correspond well with simulation results. The output beam has a Gaussian mode content of more than 99.8 % for all operating frequencies. So far, the pulse length was limited to 12{mu}s, because the electron beam recovery system was not yet installed. This system, an electron decelerator and a 3-stage depressed collector, is presently under construction. It serves to recover the charge and energy of the spend electron beam. In this paper we will address some aspects of the design of the collector. (author)

The fusion-FEM: 0,75 MW of mm-wave power

International Nuclear Information System (INIS)

Smeets, P.H.M.; Bongers, W.A.; Brons, S.; Geer, C.A.J. van der; Lingier, K.L.; Manintveld, P.; Plomp, J.; Pluygers, J.; Poelman, A.J.; Sterk, A.B.; Verhoeven, A.G.A.; Urbanus, W.H.; Bratman, V.L.; Denisov, G.G.; Savilov, A.V.; Caplan, M.; Varfolomeev, A.A.

1998-01-01

The free-electron maser for fusion applications (Fusion-FEM) is the prototype for a high power, rapid tunable mm-wave source. The basic parameters such as frequency range (130 - 260 GHz) and output power (1 MW) are dedicated to Electron Cyclotron Resonance applications on future plasma fusion research devices, such as ITER. In October 1996 the electron beam was successfully accelerated and transported through the undulator and the mm-wave cavity. Loss currents are below 0.05 %. In October 1997 first lasing was achieved. The mm-wave output power has been measured at various frequencies and for various electron beam currents and energies. The highest output power reached so far is 730 kW at 205 GHz, for an electron beam of 7.2 A and 1.77 MeV. Both output power and start-up time correspond well with simulation results. The output beam has a Gaussian mode content of more than 99.8 % for all operating frequencies. So far, the pulse length was limited to 12μs, because the electron beam recovery system was not yet installed. This system, an electron decelerator and a 3-stage depressed collector, is presently under construction. It serves to recover the charge and energy of the spend electron beam. In this paper we will address some aspects of the design of the collector. (author)

Lawrence Livermore Laboratory heavy ion fusion program

International Nuclear Information System (INIS)

Bangerter, R.O.; Lee, E.P.; Monsler, M.J.; Yu, S.S.

1978-01-01

Target design at LLL for heavy ion fusion power production is discussed, including target development and beam-target interaction. The energy conversion chamber design, which utilizes a liquid lithium blanket, is described. Ion beam transport theory is discussed

Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors

International Nuclear Information System (INIS)

Kobori, Hikaru; Kasada, Ryuta; Hiwatari, Ryoji; Konishi, Satoshi

2016-01-01

Highlights: • We incorporated the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code. • We calculated CO_2 emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. • We found that the objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. • The tokamak fusion reactor can reduce CO_2 emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. • The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant. - Abstract: This study incorporate the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code to calculate CO_2 emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. Competitiveness of tokamak fusion power reactors is expected to be evaluated by the cost and environmental impact represented by the CO_2 emissions, compared with present and future power generating systems such as fossil, nuclear and renewables. Result indicated that (1) The objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. (2) The tokamak fusion reactor can reduce CO_2 emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. (3) The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant.

Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors

Energy Technology Data Exchange (ETDEWEB)

Kobori, Hikaru [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Kasada, Ryuta, E-mail: r-kasada@iae.kyoto-u.ac.jp [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Hiwatari, Ryoji [Central Research Institute of Electric Power Industry, Tokyo (Japan); Konishi, Satoshi [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)

2016-11-01

Highlights: • We incorporated the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code. • We calculated CO{sub 2} emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. • We found that the objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. • The tokamak fusion reactor can reduce CO{sub 2} emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. • The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant. - Abstract: This study incorporate the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code to calculate CO{sub 2} emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. Competitiveness of tokamak fusion power reactors is expected to be evaluated by the cost and environmental impact represented by the CO{sub 2} emissions, compared with present and future power generating systems such as fossil, nuclear and renewables. Result indicated that (1) The objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. (2) The tokamak fusion reactor can reduce CO{sub 2} emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. (3) The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant.

Divertor conceptual designs for a fusion power plant

International Nuclear Information System (INIS)

Norajitra, P.; Ihli, T.; Janeschitz, G.; Abdel-Khalik, S.; Mazul, I.; Malang, S.

2007-01-01

The development of a divertor concept for post-ITER fusion power plants is deemed to be an urgent task to meet the EU Fast Track scenario. Developing a divertor is particularly challenging due to the wide range of requirements to be met including the high incident peak heat flux, the blanket design with which the divertor has to be integrated, sputtering erosion of the plasma-facing material caused by the incident a particles, radiation effects on the properties of structural materials, and efficient recovery and conversion of the divertor thermal power (∝15% of the total fusion thermal power) by maximizing the coolant operating temperature while minimizing the pumping power. In the course of the EU PPCS, three near-term (A, B and AB) and two advanced power plant models (C, D) were investigated. Model A utilizes a water-cooled lead-lithium (WCLL) blanket and a water-cooled divertor with a peak heat flux of 15 MW/m 2 . Model B uses a He-cooled ceramics/beryllium pebble bed (HCPB) blanket and a He-cooled divertor concept (10 MW/m 2 ). Model AB uses a He-cooled lithium-lead (HCLL) blanket and a He-cooled divertor concept (10 MW/m 2 ). Model C is based on a dual-coolant (DC) blanket (lead/lithium self-cooled bulk and He-cooled structures) and a He-cooled divertor (10 MW/m 2 ). Model D employs a self-cooled lead/lithium (SCLL) blanket and lead-lithiumcooled divertor (5 MW/m 2 ). The values in parenthesis correspond to the maximum peak heat fluxes required. It can be noted that the helium-cooled divertor is used in most of the EU plant models; it has also been proposed for the US ARIES-CS reactor study. Since 2002, it has been investigated extensively in Europe under the PPCS with the goal of reaching a maximum heat flux of at least 10 MW/m2. Work has covered many areas including conceptual design, analysis, material and fabrication issues, and experiments. Generally, the helium-cooled divertor is considered to be a suitable solution for fusion power plants, as it

Advanced fusion technology research and development. Annual report to the U.S. Department of Energy

International Nuclear Information System (INIS)

2001-01-01

OAK-B135 The General Atomics (GA) Advanced Fusion Technology program seeks to advance the knowledge base needed for next-generation fusion experiments, and ultimately for an economical and environmentally attractive fusion energy source. To achieve this objective, they carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. The technology development activities take full advantage of the GA DIII-D program, the DIII-D facility, the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility. The report summarizes GA's FY00 work in the areas of Fusion Power Plant Studies, Next Step Options, Advanced Liquid Plasma Facing Surfaces, Advanced Power Extraction Study, Plasma Interactive Materials, Radiation Testing of Magnetic Coil, Vanadium Component Demonstration, RF Technology, Inertial Fusion Energy Target Supply System, ARIES Integrated System Studies, and Spin-offs Brochure. The work in these areas continues to address many of the issues that must be resolved for the successful construction and operation of next-generation experiments and, ultimately, the development of safe, reliable, economic fusion power plants

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

Status of the US inertial fusion program and the National Ignition Facility

International Nuclear Information System (INIS)

Crandall, D.H.

1997-01-01

Research programs supported by the United States Office of Inertial Fusion and the NIF are summarized. The US inertial fusion program has developed an approach to high energy density physics and fusion ignition in the laboratory relying on the current physics basis of capsule drive by lasers and on the National Ignition Facility which is under construction. (AIP) copyright 1997 American Institute of Physics

Overview of the TITAN-II reversed-field pinch aqueous fusion power core design

Energy Technology Data Exchange (ETDEWEB)

Wong, C.P.C.; Creedon, R.L.; Grotz, S.; Cheng, E.T.; Sharafat, S.; Cooke, P.I.H.

1988-03-01

TITAN-II is a compact, high power density Reversed-Field Pinch fusion power reactor design based on the aqueous lithium solution fusion power core concept. The selected breeding and structural materials are LiNO/sub 3/ and 9-C low activation ferritic steel, respectively. TITAN-II is a viable alternative to the TITAN-I lithium self-cooled design for the Reversed-Field Pinch reactor to operate at a neutron wall loading of 18 MWm/sup 2/. Submerging the complete fusion power core and the primary loop in a large pool of cool water will minimize the probability of radioactivity release. Since the protection of the large pool integrity is the only requirement for the protection of the public, TITAN-II is a passive safety assurance design. 13 refs., 3 figs., 1 tab.

Overview of the TITAN-II reversed-field pinch aqueous fusion power core design

Energy Technology Data Exchange (ETDEWEB)

Wong, C.P.C.; Creedon, R.L.; Cheng, E.T. (General Atomic Co., San Diego, CA (USA)); Grotz, S.P.; Sharafat, S.; Cooke, P.I.H. (California Univ., Los Angeles (USA). Dept. of Mechanical, Aerospace and Nuclear Engineering; California Univ., Los Angeles, CA (USA). Inst. for Plasma and Fusion Research); TITAN Research Group

1989-04-01

TITAN-II is a compact, high-power-density Reversed-Field Pinch fusion power reactor design based on the aqueous lithium solution fusion power core concept. The selected breeding and structural materials are LiNO/sub 3/ and 9-C low activation ferritic steel, respectively. TITAN-II is a viable alternative to the TITAN-I lithium self-cooled design for the Reversed-Field Pinch reactor to operate at a neutron wall loading of 18 MW/m/sup 2/. Submerging the complete fusion power core and the primary loop in a large pool of cool water will minimize the probability of radioactivity release. Since the protection of the large pool integrity is the only requirement for the protection of the public, TITAN-II is a level 2 of passive safety assurance design. (orig.).

Fusion energy for the 21st century

International Nuclear Information System (INIS)

Harris, J.H.

1999-01-01

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

Fusion Simulation Program Definition. Final report

International Nuclear Information System (INIS)

Cary, John R.

2012-01-01

We have completed our contributions to the Fusion Simulation Program Definition Project. Our contributions were in the overall planning with concentration in the definition of the area of Software Integration and Support. We contributed to the planning of multiple meetings, and we contributed to multiple planning documents

High-Power Microwave Transmission and Mode Conversion Program

Energy Technology Data Exchange (ETDEWEB)

Vernon, Ronald J. [Univ. of Wisconsin, Madison, WI (United States)

2015-08-14

This is a final technical report for a long term project to develop improved designs and design tools for the microwave hardware and components associated with the DOE Plasma Fusion Program. We have developed basic theory, software, fabrication techniques, and low-power measurement techniques for the design of microwave hardware associated gyrotrons, microwave mode converters and high-power microwave transmission lines. Specifically, in this report we discuss our work on designing quasi-optical mode converters for single and multiple frequencies, a new method for the analysis of perturbed-wall waveguide mode converters, perturbed-wall launcher design for TE0n mode gyrotrons, quasi-optical traveling-wave resonator design for high-power testing of microwave components, and possible improvements to the HSX microwave transmission line.

Power balancing of multibeam laser fusion lasers

International Nuclear Information System (INIS)

Seka, W.; Morse, S.; Letzring, S.; Kremens, R.; Kessler, T.J.; Jaanimagi, P.; Keck, R.; Verdon, C.; Brown, D.

1989-01-01

The success of laser fusion depends to a good degree on the ability to compress the target to very high densities of ≥1000 times liquid DT. To achieve such compressions require that the irradiation nonuniformity must not exceed ∼1% rms over the whole time of the compression, particularly during the early phases of irradiation. The stringent requirements for the irradiation uniformity for laser fusion have been known for quite some time but until recently the energy balance was mistakenly equated to power balance. The authors describe their effort on energy balance and irradiation patterns on the target. They significantly improved the laser performance with respect to overall intensity distributions on target including the implementation of distributed (random) phase plates in each high power beam. However, the slightly varying performance of the third harmonic conversion crystals in the twenty-four beams of their laser system was generally compensated for by appropriately adjusted 1.054μm input laser energy. Computational analysis of the results of the recent high density campaign are shown

Civilian applications of particle-beam-initiated inertial confinement fusion technology

International Nuclear Information System (INIS)

Varnado, S.G.; Mitchiner, J.L.

1977-05-01

Electrical power generation by controlled fusion may provide a partial solution to the world's long-term energy supply problem. Achievement of a fusion reaction requires the confinement of an extremely hot plasma for a time long enough to allow fuel burnup. Inertial confinement of the plasma may be possible through the use of tightly focused, relativistic electron or ion beams to compress a fuel pellet. The Sandia Particle Beam Fusion program is developing the particle-beam accelerators necessary to achieve fuel ignition. In this report we review the status of the particle-beam fusion technology development program and identify several potential civilian applications for this technology. We describe program objectives, discuss the specific accelerators presently under development, and briefly review the results of beam-focusing and target-irradiation experiments. Then we identify and discuss applications for the beam technology and for the fusion neutrons. The applications are grouped into near-term, intermediate-term, and long-term categories. Near-term applications for the beam technology include electron-beam (e-beam) pumping of gas lasers and several commercial applications. Intermediate-term applications (pellet gain less than 50) include hybrid reactors for electrical power production and fissile fuel breeding, pure fusion reactors for electrical power production, and medical therapy using ion accelerators. In the long term, complex, high-gain pellets may be used in pure fusion reactors

Fusion by 1990: the Sandia ion beam program can do it

International Nuclear Information System (INIS)

Stevens, C.B.

1985-01-01

Recent experimental results at Sandia National Laboratories demonstrate that light ion beam accelerator devices can deliver considerably more than the power necessary for achieving high-gain fusion energy - millions of joules at power densities of 10,000 trillion watts/cm 2 . This means that commercial fusion energy with an inertial-confinement fusion device can be realized by the 1990s, despite the general curtailment of the US fusion research budget over the past eight years. Dr. J. Pace VanDevender, pulsed power sciences director at Sandia, and Professor Ravindra N. Sudan, director of the Cornell University Laboratory of Plasma Studies, discussed the experimental and theoretical advances underlying this happy prognosis at the April 17-19 conference at the Rochester University for Laser Energetics. Sudan showed that experiments with high-current ion beam pulses over the past decade have demonstrated that such pulses, instead of diffusing, tend to self-focus nonlinearly to higher power densities. Second, weak magnetic fields do not interact and change the trajectory of such high-current beam pulses. At the Rochester meeting, VanDevender reviewed experiments on Sandia's Proto I device in which 1.5 trillion watts per square centimeter were delivered to a target in May 1984. This spring, Sandia's Particle Beam Fusion Accelerator I, PBFA I, delivered an 8-trillion watt pulse onto a spot 4.0 to 4.5 millimeters in diameter. This demonstrated that the Sandia light ion beam focusing process maintains itself as the current is increased. 3 figures

Fusion reactor design and technology program in China

International Nuclear Information System (INIS)

Huang, J.H.

1994-01-01

A fusion-fission hybrid reactor program was launched in 1987. The purpose of development of the hybrid reactor is twofold: to solve the problem of nuclear fuel supply for an expected large-scale development of fission reactor plants, and to maintain the momentum of fusion research. The program is described and the activities and progress of the program are presented. Two conceptual designs of an engineering test reactor with tokamak configuration were developed at the Southwestern Institute of Physics and the Institute of Plasma Physics. The results are a tokamak engineering test breeder (TETB) series design and a fusion-fission hybrid reactor design (SSEHR), characterized by a liquid-Li self-cooled blanket and an He-cooled solid tritium breeder blanket respectively. In parallel with the design studies, relevant technological experiments on a small or medium scale have been supported by this program. These include LHCD, ICRH and pellet injection in the area of plasma engineering; neutronics integral experiments with U, Pu, Fe and Be; various irradiation tests of austenitic and ferritic steels, magnetohydrodynamic (MHD) pressure drop experiments using a liquid metal loop; research into permeation barriers for tritium and hydrogen isotopes; solid tritium breeder tests using an in-situ loop in a fission reactor. All these experiments have proceeded successfully. The second step of this program is now starting. It seems reasonable that most of the research carried out in the first step will continue. ((orig.))

Commercial feasibility of fusion power based on the tokamak concept

International Nuclear Information System (INIS)

Reid, R.L.; Steiner, D.

1977-01-01

The impact of plasma operating characteristics, engineering options, and technology on the capital cost trends of tokamak power plants is determined. Tokamak power systems are compared to other advanced energy systems and found to be economically competitive. A three-phase strategy for demonstrating commercial feasibility of fusion power, based on a common-site multiple-unit concept, is presented

Opportunistic replacement of fusion power system parts

International Nuclear Information System (INIS)

Day, J.A.; George, L.L.

1981-01-01

This paper describes a maintenance problem in a fusion power plant. The problem is to specify which life limited parts should be replaced when there is an opportunity. The objective is to minimize the cost rate of replacement parts and of maintenance actions while satisfying a power plant availability constraint. The maintenance policy is to look ahead and replace all parts that will reach their life limits within a time called a screen. Longer screens yield greater system availabilities because more parts are replaced prior to their life limits

Z-inertial fusion energy: power plant final report FY 2006.

Energy Technology Data Exchange (ETDEWEB)

Anderson, Mark (University of Wisconsin, Madison, WI); Kulcinski, Gerald (University of Wisconsin, Madison, WI); Zhao, Haihua (University of California, Berkeley, CA); Cipiti, Benjamin B.; Olson, Craig Lee; Sierra, Dannelle P.; Meier, Wayne (Lawrence Livermore National Laboratories); McConnell, Paul E.; Ghiaasiaan, M. (Georgia Institute of Technology, Atlanta, GA); Kern, Brian (Georgia Institute of Technology, Atlanta, GA); Tajima, Yu (University of California, Los Angeles, CA); Campen, Chistopher (University of California, Berkeley, CA); Sketchley, Tomas (University of California, Los Angeles, CA); Moir, R (Lawrence Livermore National Laboratories); Bardet, Philippe M. (University of California, Berkeley, CA); Durbin, Samuel; Morrow, Charles W.; Vigil, Virginia L (University of Wisconsin, Madison, WI); Modesto-Beato, Marcos A.; Franklin, James Kenneth (University of California, Berkeley, CA); Smith, James Dean; Ying, Alice (University of California, Los Angeles, CA); Cook, Jason T.; Schmitz, Lothar (University of California, Los Angeles, CA); Abdel-Khalik, S. (Georgia Institute of Technology, Atlanta, GA); Farnum, Cathy Ottinger; Abdou, Mohamed A. (University of California, Los Angeles, CA); Bonazza, Riccardo (University of Wisconsin, Madison, WI); Rodriguez, Salvador B.; Sridharan, Kumar (University of Wisconsin, Madison, WI); Rochau, Gary Eugene; Gudmundson, Jesse (University of Wisconsin, Madison, WI); Peterson, Per F. (University of California, Berkeley, CA); Marriott, Ed (University of Wisconsin, Madison, WI); Oakley, Jason (University of Wisconsin, Madison, WI)

2006-10-01

This report summarizes the work conducted for the Z-inertial fusion energy (Z-IFE) late start Laboratory Directed Research Project. A major area of focus was on creating a roadmap to a z-pinch driven fusion power plant. The roadmap ties ZIFE into the Global Nuclear Energy Partnership (GNEP) initiative through the use of high energy fusion neutrons to burn the actinides of spent fuel waste. Transmutation presents a near term use for Z-IFE technology and will aid in paving the path to fusion energy. The work this year continued to develop the science and engineering needed to support the Z-IFE roadmap. This included plant system and driver cost estimates, recyclable transmission line studies, flibe characterization, reaction chamber design, and shock mitigation techniques.

Z-inertial fusion energy: power plant final report FY 2006

International Nuclear Information System (INIS)

Anderson, Mark; Kulcinski, Gerald; Zhao, Haihua; Cipiti, Benjamin B.; Olson, Craig Lee; Sierra, Dannelle P.; Meier, Wayne; McConnell, Paul E.; Ghiaasiaan, M.; Kern, Brian; Tajima, Yu; Campen, Chistopher; Sketchley, Tomas; Moir, R; Bardet, Philippe M.; Durbin, Samuel; Morrow, Charles W.; Vigil, Virginia L.; Modesto-Beato, Marcos A.; Franklin, James Kenneth; Smith, James Dean; Ying, Alice; Cook, Jason T.; Schmitz, Lothar; Abdel-Khalik, S.; Farnum, Cathy Ottinger; Abdou, Mohamed A.; Bonazza, Riccardo; Rodriguez, Salvador B.; Sridharan, Kumar; Rochau, Gary Eugene; Gudmundson, Jesse; Peterson, Per F.; Marriott, Ed; Oakley, Jason

2006-01-01

This report summarizes the work conducted for the Z-inertial fusion energy (Z-IFE) late start Laboratory Directed Research Project. A major area of focus was on creating a roadmap to a z-pinch driven fusion power plant. The roadmap ties ZIFE into the Global Nuclear Energy Partnership (GNEP) initiative through the use of high energy fusion neutrons to burn the actinides of spent fuel waste. Transmutation presents a near term use for Z-IFE technology and will aid in paving the path to fusion energy. The work this year continued to develop the science and engineering needed to support the Z-IFE roadmap. This included plant system and driver cost estimates, recyclable transmission line studies, flibe characterization, reaction chamber design, and shock mitigation techniques

Fusion power production from TFTR plasmas fueled with deuterium and tritium

International Nuclear Information System (INIS)

Strachan, J.D.; Adler, H.; Alling, P.

1994-03-01

Peak fusion power production of 6.2 ± 0.4 MW has been achieved in TFTR plasmas heated by deuterium and tritium neutral beams at a total power of 29.5 MW. These plasmas have an inferred central fusion alpha particle density of 1.2 x 10 17 m -3 without the appearance of either disruptive MHD events or detectable changes in Alfven wave activity. The measured loss rate of energetic alpha particles agreed with the approximately 5% losses expected from alpha particles which are born on unconfined orbits

Initial progress in the first wall, blanket, and shield Engineering Test Program for magnetically confined fusion-power reactors

International Nuclear Information System (INIS)

Herman, H.; Baker, C.C.; Maroni, V.A.

1981-10-01

The first wall/blanket/shield (FW/B/S) Engineering Test Program (ETP) progressed from the planning stage into implementation during July, 1981. The program, generic in nature, comprises four Test Program Elements (TPE's), the emphasis of which is on defining the performance parameters for the Fusion Engineering Device (FED) and the major fusion device to follow FED. These elements are: (1) nonnuclear thermal-hydraulic and thermomechanical testing of first wall and component facsimiles with emphasis on surface heat loads and heat transient (i.e., plasma disruption) effects; (2) nonnuclear and nuclear testing of FW/B/S components and assemblies with emphasis on bulk (nuclear) heating effects, integrated FW/B/S hydraulics and mechanics, blanket coolant system transients, and nuclear benchmarks; (3) FW/B/S electromagnetic and eddy current effects testing, including pulsed field penetration, torque and force restraint, electromagnetic materials, liquid metal MHD effects and the like; and (4) FW/B/S Assembly, Maintenance and Repair (AMR) studies focusing on generic AMR criteria, with the objective of preparing an AMR designers guidebook; also, development of rapid remote assembly/disassembly joint system technology, leak detection and remote handling methods

Factors affecting potential market penetration of laser fusion power plants

International Nuclear Information System (INIS)

Deonigi, D.E.; Fraley, D.W.

1979-08-01

A mini-model has been constructed to estimate the optimal size of laser fusion power plants and to estimate the allowable cost of the first such plant in relation to the next best alternative. In estimating the costs of laser fusion, the mini-model incorporates such factors as market penetration, learning, economies of scale, system size, transmission costs, reserve requirements, development and licensing costs and site costs. The results of the mini-model simulations indicate that the optimal laser fusion plant size is approximately 3 GWe; risk considerations unincorporated in the mini-model suggest an optimal size closer to 2.5 GWe

The ARIES-ST study: Assessment of the spherical tokamak concept as fusion power plants

International Nuclear Information System (INIS)

Najmabadi, F.; Tillack, M.; Miller, R.; Mau, T.K.; Jardin, S.; Stambaugh, R.; Steiner, D.; Waganer, L.

2001-01-01

Recent experimental achievements and theoretical studies have generated substantial interest in the spherical tokamak concept. The ARIES-ST study was undertaken as a national U.S. effort to investigate the potential of the spherical tokamak concept as a fusion power plant and as a vehicle for fusion development. The 1000-MWe ARIES-ST power plant has an aspect ratio of 1.6, a major radius of 3.2 m, a plasma elongation (at 95% flux surface) of 3.4 and triangularity of 0.64. This configuration attains a β of 54% (which is 90% of the maximum theoretical β). While the plasma current is 31 MA, the almost perfect alignment of bootstrap and equilibrium current density profiles results in a current-drive power of only 31 MW. The on-axis toroidal field is 2.1 T and the peak field at the TF coil is 7.6 T, which leads to 288 MW of Joule losses in the normal-conducting TF system. The ARIES-ST study has highlighted many areas where tradeoffs among physics and engineering systems are critical in determining the optimum regime of operation for spherical tokamaks. Many critical issues also have been identified which must be resolved in R and D programs. (author)

Fusion looks to the future - again

International Nuclear Information System (INIS)

Waldrop, M.M.

1984-01-01

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

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

Progress in heavy-ion drivers for inertial fusion

International Nuclear Information System (INIS)

Friedman, A.; Bangerter, R.O.; Herrmannsfeldt, W.B.

1995-01-01

This document deals with heavy-ion induction accelerators developed as fusion drivers for Inertial Confinement Fusion power. It presents the results of research aimed at developing drivers having reduced cost and size as well as the Elise accelerator being built at Lawrence Berkeley Laboratory. An experimental program at Lawrence Livermore National Laboratory concerning recirculating induction accelerators is also presented. Eventually, the document provides some information on other elements of the U.S. Heavy-Ion Fusion (HIF) research program: the experimental study of beam merging, a magnetic quadrupole development program and a study of plasma lenses. (TEC). 28 refs., 6 figs

Portuguese research program on nuclear fusion

International Nuclear Information System (INIS)

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

1994-01-01

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

Economic comparison of fusion power plant designs

International Nuclear Information System (INIS)

O'Neill, J.E.

1986-01-01

Over the past 10 yr, a number of studies have been developed for fusion power plants of various types (tokamaks, mirrors, etc.) complete with figures of merit such as cost estimates and estimates of the cost of generating electricity (COE). Each of these designs involves unresolved physics and engineering problems which, it is assumed, will eventually be worked out. Because of such uncertainties the figures of merit associated with such designs are not to be compared as absolute measures of worth but as relative indicators of progress within a given concept type. As part of Grumman's involvement in fusion energy development, an effort has been undertaken to compare economic indicators from the referenced studies in order to determine the cost trend in recent reactor design activities

Challenges and the future of the fusion energy

International Nuclear Information System (INIS)

Gross, R.A.

1982-01-01

The need to develop new large energy resources is discussed. One of three inexhaustible energy resource possibilities is fusion energy, whose history and scientific goals are described. The current world-wide research and development program for fusion is outlined. As an example of today's perception of what fusion energy will be like, a commercial tokamak fusion electric powerplant is described. Special attention is devoted to some of the challenging material problems that face fusion power development. (Author) [pt

Review of alternative concepts for magnetic fusion

International Nuclear Information System (INIS)

Krakowski, R.A.; Miller, R.L.; Hagenson, R.L.

1980-01-01

Although the Tokamak represents the mainstay of the world's quest for magnetic fusion power, with the tandem mirror serving as a primary backup concept in the US fusion program, a wide range of alternative fusion concepts (AFC's) have been and are being pursued. This review presents a summary of past and present reactor projections of a majority of AFC's. Whenever possible, quantitative results are given

Fusion technology development annual report, October 1, 1995--September 30, 1996

International Nuclear Information System (INIS)

1997-03-01

In FY96, the General Atomics (GA) Fusion Group made significant contributions to the technology needs of the magnetic fusion program. The work is reported in the following sections on Fusion Power Plant Design Studies (Section 2), Plasma Interactive Materials (Section 3), SiC/SiC Composite Material Development (Section 4), Magnetic Diagnostic Probes (Section 5) and RF Technology (Section 6). Meetings attended and publications are listed in their respective sections. The overall objective of GA's fusion technology research is to develop the technologies necessary for fusion to move successfully from present-day physics experiments to ITER and other next-generation fusion experiments, and ultimately to fusion power plants. To achieve this overall objective, the authors carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic knowledge about these technologies, including plasma technologies, fusion nuclear technologies, and fusion materials. They continue to be committed to the development of fusion power and its commercialization by US industry

Role of supercomputers in magnetic fusion and energy research programs

International Nuclear Information System (INIS)

Killeen, J.

1985-06-01

The importance of computer modeling in magnetic fusion (MFE) and energy research (ER) programs is discussed. The need for the most advanced supercomputers is described, and the role of the National Magnetic Fusion Energy Computer Center in meeting these needs is explained

Massachusetts Institute of Technology, Plasma Fusion Center, technical research programs

International Nuclear Information System (INIS)

1982-02-01

Research programs have produced significant results on four fronts: (1) the basic physics of high-temperature fusion plasmas (plasma theory, RF heating, development of advanced diagnostics and small-scale experiments on the Versator tokamak and Constance mirror devices); (2) major confinement results on the Alcator A and C tokamaks, including pioneering investigations of the equilibrium, stability, transport and radiation properties of fusion plasmas at high densities, temperatures and magnetic fields; (3) development of a new and innovative design for axisymmetric tandem mirrors with inboard thermal barriers, with initial operation of the TARA tandem mirror experimental facility scheduled for 1983; and (4) a broadly based program of fusion technology and engineering development that addresses problems in several critical subsystem areas

The status of the federal magnetic fusion program, or fusion in transition: from science to technology

International Nuclear Information System (INIS)

Kane, J.S.

1983-01-01

The current status of magnetic fusion is summarized. The science is in place; the application must be made. Government will have to underwrite the risk of the program, but the private sector must manage it. Government officials must be convinced fusion is in the interest of the taxpayer, private sector decision makers that it is commercial. Questions concerning reliability, availability, first cost, safety, environment, and sociology must be asked. Fusion energy is essentially inexhaustible, appears environmentally acceptable, and is one of a very short list of alternatives

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

Electron-beam-fusion progress report, January--June 1976

International Nuclear Information System (INIS)

1976-10-01

Research progress is reported for the following areas: (1) Proto I, (2) Proto II, (3) EBFA, (4) power flow, (5) contract progress reports, (6) progress in the Sandia program, (7) repetitively operated pulse generator development, (8) electron beam power from inductive storage, (9) fusion target design, (10) beam physics research, (11) power flow, (12) heavy ion fusion, (13) particle beam source development, (14) beam target interaction and target response studies, (15) diagnostic development, and (16) hybrid systems

CFARMHD -- A MathCAD PC program to evaluate performance and economics of CFARII fusion reactors

International Nuclear Information System (INIS)

Logan, B.G.

1992-01-01

This report describes a PC computer program ''CFARMHD'', developed to evaluate the performance (MHD cycle efficiency) and economics (Cost-of-Electricity CoE) for pulsed fusion reactors using the Compact Fusion Advanced Rankine II (CFARII) MHD Balance of Plant (BoP). The CFARII concept to which this code applies is generic to any fusion driver which can be characterized by an assumed yield Y (GJ), target gain G, and unit cost ($/joule driver). The CFARMHD code models the sizes, masses, energies, mass flows and powers corresponding to the physical systems and optimizes them to minimize CoE for given Y, G, $/joule, and choice of material for the working fluid (cast as solid spherical shells around the target). A description of the models used in the CFARMHD code is given in Section 11, and the CoE minimization procedure used in the code is described in Section III

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.

Fusion Research Center, theory program. Progress report

International Nuclear Information System (INIS)

1982-01-01

The Texas FRC theory program is directed primarily toward understanding the initiation, heating, and confinement of tokamak plasmas. It supports and complements the experimental programs on the TEXT and PRETEXT devices, as well as providing information generally applicable to the national tokamak program. A significant fraction of the Center's work has been carried out in collaboration with, or as a part of, the program of the Institute for Fusion Studies (IFS). During the past twelve months, 14 FRC theory reports and 12 IFS reports with partial FRC support have been issued

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

International Nuclear Information System (INIS)

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

2006-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-07-01

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

Summaries of FY 1986 research in the Applied Plasma Physics Fusion Theory Program

International Nuclear Information System (INIS)

1987-12-01

The Theory Program is charged with supporting the development of theories and models of plasmas for the fusion research effort. This work ranges from first-principles analysis of elementary plasma processes to empirical simulation of specific experiments. The Theory Program supports research by industrial contractors, US government laboratories, and universities. The university support also helps to fulfill the DOE mission of training scientists for the fusion program. The Theory Program is funded through the Fusion Theory Branch, Division of Applied Plasma Physics in the Office of Fusion Energy. The work is divided among 31 institutions, of which 19 are universities, five are industrial contractors, and seven are US government laboratories; see Table 1 for a complete list. The FY 1986 Theory Program budget was divided among theory types: toroidal, mirror, alternate concept, generic, and atomic. Device modeling is included among the other funding categories, and is not budgeted separately

Effects of waste management on the impact of fusion power

International Nuclear Information System (INIS)

Botts, T.; Powell, J.

1978-01-01

Throughputs and inventories of radioactive materials that would have to be managed by a country whose primary form of electrical generation is fusion are estimated. Whole body dose rates for the entire population due to normal and off-normal incidents are calculated. For the case of equilibrium systems, two fusion cases are compared to an advanced fission power case. Comparisons are made for various stages of the fuel cycle and activated materials cycles. Fission reactor radiological impact is dominated by fuel reprocessing facility releases. These releases will decrease significantly if methods of containing 85 Kr are implemented. Tritium releases during normal plant operations comprise most of the radiologic impact for both fusion cases. Total dose rates are estimated to be roughly two orders of magnitude lower for fusion than for fission reactors

Osiris and SOMBRERO inertial confinement fusion power plant designs

International Nuclear Information System (INIS)

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01

The primary objective of the of the IFE Reactor Design Studies was to provide the Office of Fusion Energy with an evaluation of the potential of inertial fusion for electric power production. The term reactor studies is somewhat of a misnomer since these studies included the conceptual design and analysis of all aspects of the IFE power plants: the chambers, heat transport and power conversion systems, other balance of plant facilities, target systems (including the target production, injection, and tracking systems), and the two drivers. The scope of the IFE Reactor Design Studies was quite ambitious. The majority of our effort was spent on the conceptual design of two IFE electric power plants, one using an induction linac heavy ion beam (HIB) driver and the other using a Krypton Fluoride (KrF) laser driver. After the two point designs were developed, they were assessed in terms of their (1) environmental and safety aspects; (2) reliability, availability, and maintainability; (3) technical issues and technology development requirements; and (4) economics. Finally, we compared the design features and the results of the assessments for the two designs

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)

Review of the Inertial Fusion Energy Program

Energy Technology Data Exchange (ETDEWEB)

none,

2004-03-29

Igniting fusion fuel in the laboratory remains an alluring goal for two reasons: the desire to study matter under the extreme conditions needed for fusion burn, and the potential of harnessing the energy released as an attractive energy source for mankind. The inertial confinement approach to fusion involves rapidly compressing a tiny spherical capsule of fuel, initially a few millimeters in radius, to densities and temperatures higher than those in the core of the sun. The ignited plasma is confined solely by its own inertia long enough for a significant fraction of the fuel to burn before the plasma expands, cools down and the fusion reactions are quenched. The potential of this confinement approach as an attractive energy source is being studied in the Inertial Fusion Energy (IFE) program, which is the subject of this report. A complex set of interrelated requirements for IFE has motivated the study of novel potential solutions. Three types of “drivers” for fuel compression are presently studied: high-averagepower lasers (HAPL), heavy-ion (HI) accelerators, and Z-Pinches. The three main approaches to IFE are based on these drivers, along with the specific type of target (which contains the fuel capsule) and chamber that appear most promising for a particular driver.

Review of the Inertial Fusion Energy Program

International Nuclear Information System (INIS)

2004-01-01

Igniting fusion fuel in the laboratory remains an alluring goal for two reasons: the desire to study matter under the extreme conditions needed for fusion burn, and the potential of harnessing the energy released as an attractive energy source for mankind. The inertial confinement approach to fusion involves rapidly compressing a tiny spherical capsule of fuel, initially a few millimeters in radius, to densities and temperatures higher than those in the core of the sun. The ignited plasma is confined solely by its own inertia long enough for a significant fraction of the fuel to burn before the plasma expands, cools down and the fusion reactions are quenched. The potential of this confinement approach as an attractive energy source is being studied in the Inertial Fusion Energy (IFE) program, which is the subject of this report. A complex set of interrelated requirements for IFE has motivated the study of novel potential solutions. Three types of @@@drivers@@@ for fuel compression are presently studied: high-averagepower lasers (HAPL), heavy-ion (HI) accelerators, and Z-Pinches. The three main approaches to IFE are based on these drivers, along with the specific type of target (which contains the fuel capsule) and chamber that appear most promising for a particular driver.

Fusion Safety Program annual report: Fiscal year 1987

International Nuclear Information System (INIS)

Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

1988-02-01

This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

Analysis of three-phase power-supply systems using computer-aided design programs

International Nuclear Information System (INIS)

Oberst, E.F.

1977-01-01

A major concern of every designer of large, three-phase power-supply systems is the protection of system components from overvoltage transients. At present, three computer-aided circuit design programs are available in the Magnetic Fusion Energy (MFE) National Computer Center that can be used to analyze three-phase power systems: MINI SCEPTRE, SPICE I, and SPICE II. These programs have been used at Lawrence Livermore Laboratory (LLL) to analyze the operation of a 200-kV dc, 20-A acceleration power supply for the High Voltage Test Stand. Various overvoltage conditions are simulated and the effectiveness of system protective devices is observed. The simulated overvoltage conditions include such things as circuit breaker openings, pulsed loading, and commutation voltage surges in the rectifiers. These examples are used to illustrate the use of the computer-aided, circuit-design programs discussed in this paper

Fusion Implementation

International Nuclear Information System (INIS)

Schmidt, J.A.

2002-01-01

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

LLL magnetic fusion energy program: an overview

International Nuclear Information System (INIS)

Anon.

1976-01-01

Over the last 12 months, significant progress has been made in the LLL magnetic fusion energy program. In the 2XIIB experiment, a tenfold improvement was achieved in the plasma confinement factor (the product of plasma density and confinement time), pushed plasma temperature and pressure to values never before reached in a magnetic fusion experiment, and demonstrated--for the first time--plasma startup by neutral beam injection. A new laser-pellet startup technique for Baseball IIT has been successfully tested and is now being incorporated in the experiment. Technological improvements have been realized, such as a breakthrough in fabricating niobium-tin conductors for superconducting magnets. These successes, together with complementary progress in theory and reactor design, have led to a proposal to build the MX facility, which could be on the threshold of a mirror fusion reactor

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.)

Simulation of fusion power in tokamak reactor

International Nuclear Information System (INIS)

Gaber, F.A.; Elsharif, R.N.; Sayed, Y.A.

1993-01-01

The paper deals with the transient response of the fusion power against perturbation in the injection rate of the fuel to ± 10% step change. The steady state results are in good agreement with the references results. The adequacy of these study was tested by assessing the physical plausibility of the obtained result, as well as, comparison with other validated model. 2 fig., 2 tab

Development step toward fusion power plant and role of experimental reactor ITER

International Nuclear Information System (INIS)

Hiwatari, Ryouji; Asaoka, Yoshiyuki; Okano, Kunihiko

2005-01-01

The development of fusion energy is going into the experimental reactor stage, and the thermal energy from the fusion reaction will be generated in a plant scale through the ITER (International Thermonuclear Experimental Reactor) project. The remaining critical issue toward the realization of fusion energy is to map out the development strategy. Recently early realization approach as for the fusion energy development is being discussed in Japan, Europe, and the United States. This approach implies that the devices for a Demo reactor and a proto-type reactor as seen in the fast breeder reactor are combined into a single device in order to advance the fusion energy development. On the other hand, a clear development road map for fusion energy hasn't been suggested yet, and whether that early realization approach is feasible or not is still ambiguous. In order to realize the fusion energy as an user-friendly energy system, the suggestion of the development missions and the road map from the user-side point of view is instructive not only to Japanese but also to other country's development policy after the ITER project. In this report, first of all, the development missions from the user's point of view have been structured. Second, the development target required to demonstrate net electric generation and to introduce the fusion energy into the market is investigated, respectively. This investigation reveals that the completion of the ITER reference operation gives the outlook toward the demonstration of net electric generation and that the completion of the ITER advanced operation gives the possibility to introduce the fusion energy into the market. At last, the electric demonstration power plant Demo-CREST and the commercial power plant CREST are proposed to construct the development road map for fusion energy. (author)

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

International Nuclear Information System (INIS)

2008-01-01

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

Progress toward fusion with light ions

International Nuclear Information System (INIS)

1980-01-01

New results in target design, beam generation and transport, and pulse power technology have led to a program shift stressing light ion-driven inertial confinement fusion. According to present estimates, a gain ten fusion pellet will require at least one megajoule and approx. 100 TW power input. Progress in ion sources has resulted in beam power density of approx. 1 TW/cm 2 , a factor of ten increase over the last year, and cylindrical implosion experiments have been performed. Other experiments have demonstrated the ability to transport ion and electron beams with high efficiency and have confirmed numerical predictions on the properties of beam transport channels converging at a target. These developments together with improvements in pulse power technology allow us to project that the 72 beam, 100 TW Particle Beam Fusion Accelerator, PBFA-II will attain target output energy equal to stored energy in the accelerator

Advanced laser fusion target fabrication research and development proposal

International Nuclear Information System (INIS)

Stupin, D.M.; Fries, R.J.

1979-05-01

A research and development program is described that will enable the fabrication of 10 6 targets/day for a laser fusion prototype power reactor in 2007. We give personnel and cost estimates for a generalized laser fusion target that requires the development of several new technologies. The total cost of the program between 1979 and 2007 is $362 million in today's dollars

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

The reversed-field pinch: a compact approach to fusion power

International Nuclear Information System (INIS)

Hagenson, R.L.; Krakowski, R.A.; Bathke, C.G.; Miller, R.L.

1985-01-01

The potential of the reversed-field pinch (RFP) for development into an efficient, compact, copper-coil fusion reactor has been quantified by comprehensive parametric tradeoff studies. This compact system promises to be competitive in size, power density, and cost to alternative energy sources. Conceptual engineering designs that substantiate these promising results have been completed. This 1000 MW(e) (net) design is described along with a detailed rationale and physics/technology assessment for the compact approach to fusion. The RFP presents a robust plasma confinement system capable of providing a range of reactor systems that are compact in both physical size and/or net power output while ensuring acceptable cost and engineering feasibility for a range of assumed physics performance. (author)

Summary of research for the Inertial Confinement Fusion Program at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Cartwright, D.C.

1985-03-01

The information presented in this report is a summary of the status of the Inertial Confinement Fusion (ICF) program at the Los Alamos National Laboratory as of February 1985. This report contains material on the existing high-power CO 2 laser driver (Antares), the program to determine the potential of KrF as an ICF driver, heavy-ion accelerators as drivers for ICF, target fabrication for ICF, and a summary of our understanding of laser-plasma interactions. A classified companion report contains material on our current understanding of capsule physics and lists the contributions to the Laboratory's weapons programs made by the ICF program. The information collected in these two volumes is meant to serve as a report on the status of some of the technological components of the Los Alamos ICF program rather than a detailed review of specific technical issues

Liquid lithium loop system to solve challenging technology issues for fusion power plant

Science.gov (United States)

Ono, M.; Majeski, R.; Jaworski, M. A.; Hirooka, Y.; Kaita, R.; Gray, T. K.; Maingi, R.; Skinner, C. H.; Christenson, M.; Ruzic, D. N.

2017-11-01

Steady-state fusion power plant designs present major divertor technology challenges, including high divertor heat flux both in steady-state and during transients. In addition to these concerns, there are the unresolved technology issues of long term dust accumulation and associated tritium inventory and safety issues. It has been suggested that radiation-based liquid lithium (LL) divertor concepts with a modest lithium-loop could provide a possible solution for these outstanding fusion reactor technology issues, while potentially improving reactor plasma performance. The application of lithium (Li) in NSTX resulted in improved H-mode confinement, H-mode power threshold reduction, and reduction in the divertor peak heat flux while maintaining essentially Li-free core plasma operation even during H-modes. These promising results in NSTX and related modeling calculations motivated the radiative liquid lithium divertor concept and its variant, the active liquid lithium divertor concept, taking advantage of the enhanced or non-coronal Li radiation in relatively poorly confined divertor plasmas. To maintain the LL purity in a 1 GW-electric class fusion power plant, a closed LL loop system with a modest circulating capacity of ~1 l s-1 is envisioned. We examined two key technology issues: (1) dust or solid particle removal and (2) real time recovery of tritium from LL while keeping the tritium inventory level to an acceptable level. By running the LL-loop continuously, it can carry the dust particles and impurities generated in the vacuum vessel to the outside where the dust/impurities can be removed by relatively simple dust filter, cold trap and/or centrifugal separation systems. With ~1 l s-1 LL flow, even a small 0.1% dust content by weight (or 0.5 g s-1) suggests that the LL-loop could carry away nearly 16 tons of dust per year. In a 1 GW-electric (or ~3 GW fusion power) fusion power plant, about 0.5 g s-1 of tritium is needed to maintain the fusion fuel cycle

Developmental validation of the PowerPlex(®) Fusion 6C System.

Science.gov (United States)

Ensenberger, Martin G; Lenz, Kristy A; Matthies, Learden K; Hadinoto, Gregory M; Schienman, John E; Przech, Angela J; Morganti, Michael W; Renstrom, Daniel T; Baker, Victoria M; Gawrys, Kori M; Hoogendoorn, Marlijn; Steffen, Carolyn R; Martín, Pablo; Alonso, Antonio; Olson, Hope R; Sprecher, Cynthia J; Storts, Douglas R

2016-03-01

The PowerPlex(®) Fusion 6C System is a 27-locus, six-dye, multiplex that includes all markers in the expanded CODIS core loci and increases overlap with STR database standards throughout the world. Additionally, it contains two, rapidly mutating, Y-STRs and is capable of both casework and database workflows, including direct amplification. A multi-laboratory developmental validation study was performed on the PowerPlex(®) Fusion 6C System. Here, we report the results of that study which followed SWGDAM guidelines and includes data for: species specificity, sensitivity, stability, precision, reproducibility and repeatability, case-type samples, concordance, stutter, DNA mixtures, and PCR-based procedures. Where appropriate we report data from both extracted DNA samples and direct amplification samples from various substrates and collection devices. Samples from all studies were separated on both Applied Biosystems 3500 series and 6-dye capable 3130 series Genetic Analyzers and data is reported for each. Together, the data validate the design and demonstrate the performance of the PowerPlex(®) Fusion 6C System. Copyright © 2015 The Authors. Published by Elsevier Ireland Ltd.. All rights reserved.

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-01

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

Fusion Power Demonstration III

International Nuclear Information System (INIS)

Lee, J.D.

1985-07-01

This is the third in the series of reports covering the Fusion Power Demonstration (FPD) design study. This volume considers the FPD-III configuration that incorporates an octopole end plug. As compared with the quadrupole end-plugged designs of FPD-I and FPD-II, this octopole configuration reduces the number of end cell magnets and shortens the minimum ignition length of the central cell. The end-cell plasma length is also reduced, which in turn reduces the size and cost of the end cell magnets and shielding. As a contiuation in the series of documents covering the FPD, this report does not stand alone as a design description of FPD-III. Design details of FPD-III subsystems that do not differ significantly from those of the FPD-II configuration are not duplicated in this report

Safety and environmental aspects of fusion power

International Nuclear Information System (INIS)

McCarthy, K.A.

1993-01-01

Fusion power has the potential to be a safe and environmentally friendly energy source. Materials and design can limit hazards from accidental release of radioactive material and minimize waste disposal problems. In addition, no emissions are produced to degrade visibility, increase greenhouse gases, cause acid rain or reduce the ozone layer. Because of the flexibility in materials choice, recycling and near-surface burial are potential options for radioactive waste management

Powerful lasers for thermonuclear fusion

International Nuclear Information System (INIS)

Basov, N.; Krokhin, O.; Sklizkov, G.; Fedotov, S.

1977-01-01

The parameters are discussed of the radiation of powerful lasers (internal energy of the plasma determined by the volume, density and temperature of the plasma, duration of the heating pulse, focusing of the laser pulse energy in a small volume of matter, radiation contrast) for attaining an effective thermonuclear fusion at minimum microexplosion energy. A survey is given of the methods of shaping laser pulses with limit parameters, and the principle of the construction of powerful laser systems is described. The general diagram and parameters are given of the Delfin thermonuclear apparatus and a diagram is presented of the focusing system of high luminosity for spherical plasma heating using spherical mirrors. A diagram is presented of the vacuum chamber and of the complex diagnostic apparatus for determining the basic parameters of thermonuclear plasma in the Delfin apparatus. The prospects are indicated of the further development of thermonuclear laser apparatus with neodymium and CO 2 lasers. (B.S.)

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

Establishment of KAERI Strategy and Organization for Fusion Power Technology Research

International Nuclear Information System (INIS)

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

2005-04-01

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

Radioactive waste management and disposal scenario for fusion power reactors

Energy Technology Data Exchange (ETDEWEB)

Tabara, Takashi; Yamano, Naoki [Sumitomo Atomic Energy Industries Ltd., Tokyo (Japan); Seki, Yasushi; Aoki, Isao

1997-10-01

The environmental and economic impact of radioactive waste (radwaste) generated from fusion power reactors using five types of structural materials and a light water reactor (LWR) have been evaluated and compared. At first, the amount and the radioactive level of the radwaste generated in five fusion reactors ware evaluated by an activation calculation code. Next, a possible radwaste disposal scenario applicable to fusion radwaste in Japan is considered and the disposal cost evaluated under certain assumptions. The exposure doses are evaluated for the skyshine of gamma-rays during the disposal operation, groundwater migration scenario during the institutional control period of 300 years and future site use scenario after the institutional period. The radwaste generated from a typical LWR was estimated based on a literature survey and the disposal cost was evaluated using the same assumptions as for the fusion reactors. It is found that the relative cost of disposal is strongly dependent on the cost for interim storage of medium level waste of fusion reactors and the cost of high level waste for the LWR. (author)

Conceptual Design of Low Fusion Power Hybrid System for Waste Transmutation

Energy Technology Data Exchange (ETDEWEB)

Hong, Seong Hee; Kim, Myung Hyun [Kyung Hee University, Yongin (Korea, Republic of)

2016-10-15

DRUP (Direct Reuse of Used PWR) fuel has same process with DUPIC (Direct Use of spent PWR fuel Into CANDU reactor). There are 2 big benefits by using DRUP fuel in Hybrid system. One is fissile production during operating period. Required power is decreased by fissile production from DRUP fuel. When the fusion power is reduced, integrity of structure materials is not significantly weakened due to reduction of 14.1MeV high energy neutrons. In addition, required amount of tritium for self-sufficiency TBR (Tritium Breeding Ratio ≥ 1.1) is decreased. Therefore, it is possible to further loading the SNF as much as the amount of lithium decreased. It is effective in transmutation. The other one is that DRUP fuel is also SNF. Therefore, using DRUP fuel is reusing of SNF, as a result it makes reduction of SNF from PWR. However, thermal neutron system is suitable for using DRUP fuel compared to fast neutron system. Therefore, transmutation zone designed (U-TRU)Zr fuel and fissile production zone designed DRUP fuel are separated in this study. In this paper, using DRUP fuel for low fusion power in hybrid system is suggested. Fusion power is decreased by using DRUP fuel. As a result, TBR is satisfied design condition despite of using natural lithium. In addition, not only (U-TRU)Zr fuel but also DRUP fuel are transmuted.

Poloidal variations in toroidal fusion reactor wall power loadings

International Nuclear Information System (INIS)

Carroll, M.C.; Miley, G.H.

1985-01-01

A geometric formulation is developed by the authors for determining poloidal variations in bremmstrahlung, cyclotron radiation, and neutron wall power loadings in toroidal fusion devices. Assuming toroidal symmetry and utilizing a numerical model which partitions the plasma into small cells, it was generally found that power loadings are highest on the outer surface of the torus, although variations are not as large as some have predicted. Results are presented for various plasma power generation configurations, plasma volume fractions, and toroidal aspect ratios, and include plasma and wall blockage effects

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

FRESCO: fusion reactor simulation code for tokamaks

International Nuclear Information System (INIS)

Mantsinen, M.J.

1995-03-01

The study of the dynamics of tokamak fusion reactors, a zero-dimensional particle and power balance code FRESCO (Fusion Reactor Simulation Code) has been developed at the Department of Technical Physics of Helsinki University of Technology. The FRESCO code is based on zero-dimensional particle and power balance equations averaged over prescribed plasma profiles. In the report the data structure of the FRESCO code is described, including the description of the COMMON statements, program input, and program output. The general structure of the code is described, including the description of subprograms and functions. The physical model used and examples of the code performance are also included in the report. (121 tabs.) (author)

Fusion plasma physics research on the H-1 national facility

International Nuclear Information System (INIS)

Harris, J.

1998-01-01

Full text: Australia has a highly leveraged fusion plasma research program centred on the H-1 National Facility device at the ANU. H-1 is a heliac, a novel helical axis stellarator that was experimentally pioneered in Australia, but has a close correlation with the worldwide research program on toroidal confinement of fusion grade plasma. Experiments are conducted on H-1 by university researchers from the Australian Fusion Research Group (comprising groups from the ANU, the Universities of Sydney, Western Sydney, Canberra, New England, and Central Queensland University) under the aegis of AINSE; the scientists also collaborate with fusion researchers from Japan and the US. Recent experiments on H-1 have focused on improved confinement modes that can be accessed at very low powers in H-1, but allow the study of fundamental physics effects seen on much larger machines at higher powers. H-1 is now being upgraded in magnetic field and heating power, and will be able to confine hotter plasmas beginning in 1999, offering greatly enhanced research opportunities for Australian plasma scientists and engineers, with substantial spillover of ideas from fusion research into other areas of applied physics and engineering

ARIES-I Fusion-Power-Core Engineering

International Nuclear Information System (INIS)

Sharafat, S.; Najmabadi, F.; Wong, C.P.C.

1991-01-01

The ARIES research program is a multi-institutional project, the goal of which is to determine the economic, safety, and environmental potential of tokamak fusion reactors. The ARIES-I steady-state tokamak reactor is a conceptual, DT-burning, 1000 MWe reactor with a major radius of 6.75 m, a minor radius of 1.5 m, and an average neutron wall loading of 2.5 MW/m 2 . The ARIES-I plasma operates in the first MHD stability regime with a toroidal beta of 1.9%. The choice to operate in the first stability regime, with a high aspect ratio and with a low plasma current, leads to the need for high magnetic field to achieve adequate fusion power density (β 2 B 4 ). The toroidal field at the plasma center is 11 T and the maximum field at the coil is 21 T. Nonetheless, it is found that the maximum stress in the structural material of these magnets is ∝700 MPa and industrially available alloys can be used. The impurity-control and particle-exhaust system is based on a high recycling double-null divertor system. The low-activation silicon-carbide (SiC) composite is used as structural material. The breeder material, Li 2 ZrO 3 , and the multiplier material, Be, are both sphere-packed between poloidally nested SiC-composite shells. The divertor plates consist of SiC-composite tube shells protected with 2 mm-thick tungsten armor. The first wall, blanket, shield, and divertor are all helium cooled with an inlet coolant temperature of 350deg C at a pressure of 10 MPa. The high helium-outlet temperature of 650deg C ensures a relatively high gross thermal efficiency of 49%. The ARIES-I design has demonstrated that tokamak reactors have the potential to achieve a high level of safety coupled with a Class-C waste-disposal rating. (orig.)

The role of fusion power in energy scenarios. Proposed method and review of existing scenarios

International Nuclear Information System (INIS)

Lako, P; Ybema, J.R.; Seebregts, A.J.

1998-04-01

The European Commission wishes more insight in the potential role of fusion energy in the second half of the 21st century. Therefore, several scenario studies are carried out in the so-called macro-task Long Term Scenarios to investigate the potential role of fusion power in the energy system. The main contribution of ECN to the macro-task is to perform a long term energy scenario study for Western Europe with special focus on the role of fusion power. This interim report gives some methodological considerations for such an analysis. A discussion is given on the problems related to the long time horizon of the scenario study such as the forecast of technological innovations, the selection of appropriate discount rates and the links with climate change. Key parameters which are expected to have large effects on the role and cost-effectiveness are discussed in general terms. The key parameters to be varied include level and structure of energy demand, availability and prices of fossil energy, CO2 reduction policy, discount rates, cost and potential of renewable energy sources, availability of fission power and CO2 capture and disposal and the cost and the maximum rate of market growth of fusion power. The scenario calculations are to be performed later in the project with the help of an existing cost minimisation model of the Western European energy system. This MARKAL model is briefly introduced. The results of the model calculations are expected to make clear under which combinations of scenario parameters fusion power is needed and how large the expected financial benefits will be. The present interim report also gives an evaluation of existing energy scenarios with respect to the role of fusion power. 18 refs

Fusion program. The interest for the industry

International Nuclear Information System (INIS)

Dominguez Bautista, M. T.

2007-01-01

On November 21, 2006, the ministers representing all the parties taking part in ITER (EU, china, India, Japan, Rusia, USA and south Korea signed the so-called ITER agreement, thereby affirming the decision to build this fusion energy demonstration experiment. As of that moment, each partner has been preparing its Domestic Agency that will manage its contribution. Europe will play a relevant role in this facility, the site of which is located in Cadarache, and will provide 50% of its investment. This leading role of Europe is the continuation of years of decisive support for the fusion program. In successive Framework Programs of EURATOM, resources have been allotted to fusion and projects have been executed with specific organizations to coordinate them (EFDA). One of the most significant decision to accomplish this coordination was to involve the industry; in 1994, the ITER EDA Framework Contract was signed to develop the ITER engineering. Since then the EFET group, formed by seven European engineering firms including Empresarios Agrupados and Sener, has developed design work for ITER. together with these engineering activities, engineering firms and manufacturers were qualified to develop prototypes as apart of the so-called 17-technology program. these decisions have made it possible to provide ITER with the industry experience in the execution of large projects and have provided industry with a knowledge of this facility features. Now the time has come to execute the project, and the challenge will be to know how to take advantage of the experience gained by Europe. This article discusses in greater detail the areas to which the European industry has contributed and the expected conditions for this participation. (Author)

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

Prospects of High Temperature Superconductors for fusion magnets and power applications

International Nuclear Information System (INIS)

Fietz, Walter H.; Barth, Christian; Drotziger, Sandra; Goldacker, Wilfried; Heller, Reinhard; Schlachter, Sonja I.; Weiss, Klaus-Peter

2013-01-01

Highlights: • An overview of HTS application in fusion is given. • BSCCO application for current leads is discussed. • Several approaches to come to a high current HTS cable are shown. • Open issues and benefits of REBCO high current HTS cables are discussed. -- Abstract: During the last few years, progress in the field of second-generation High Temperature Superconductors (HTS) was breathtaking. Industry has taken up production of long length coated REBCO conductors with reduced angular dependency on external magnetic field and excellent critical current density jc. Consequently these REBCO tapes are used more and more in power application. For fusion magnets, high current conductors in the kA range are needed to limit the voltage during fast discharge. Several designs for high current cables using High Temperature Superconductors have been proposed. With the REBCO tape performance at hand, the prospects of fusion magnets based on such high current cables are promising. An operation at 4.5 K offers a comfortable temperature margin, more mechanical stability and the possibility to reach even higher fields compared to existing solutions with Nb 3 Sn which could be interesting with respect to DEMO. After a brief overview of HTS use in power application the paper will give an overview of possible use of HTS material for fusion application. Present high current HTS cable designs are reviewed and the potential using such concepts for future fusion magnets is discussed

Apparatus and method for extracting power from energetic ions produced in nuclear fusion

Science.gov (United States)

Fisch, Nathaniel J.; Rax, Jean M.

1994-01-01

An apparatus and method of extracting power from energetic ions produced by nuclear fusion in a toroidal plasma to enhance respectively the toroidal plasma current and fusion reactivity. By injecting waves of predetermined frequency and phase traveling substantially in a selected poloidal direction within the plasma, the energetic ions become diffused in energy and space such that the energetic ions lose energy and amplify the waves. The amplified waves are further adapted to travel substantially in a selected toroidal direction to increase preferentially the energy of electrons traveling in one toroidal direction which, in turn, enhances or generates a toroidal plasma current. In an further adaptation, the amplified waves can be made to preferentially increase the energy of fuel ions within the plasma to enhance the fusion reactivity of the fuel ions. The described direct, or in situ, conversion of the energetic ion energy provides an efficient and economical means of delivering power to a fusion reactor.

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

Exploring novel high power density concepts for attractive fusion systems

Energy Technology Data Exchange (ETDEWEB)

Abdou, M.A. [California State Univ., Los Angeles, CA (United States). Dept. of Mechanical Engineering; APEX Team

1999-05-01

The advanced power extraction study is aimed at exploring innovative concepts for fusion power technology (FPT) that can tremendously enhance the potential of fusion as an attractive and competitive energy source. Specifically, the study is exploring new and `revolutionary` concepts that can provide the capability to efficiently extract heat from systems with high neutron and surface heat loads while satisfying all the FPT functional requirements and maximizing reliability, maintainability, safety, and environmental requirements. The primary criteria for measuring performance of the new concepts are: (1) high power density capability with a peak neutron wall load (NWL) of {proportional_to}10 MW m{sup -2} and surface heat flux of {proportional_to}2 MW m{sup -2}; (2) high power conversion efficiency, {proportional_to}40% net; and (3) clear potential to achieve high availability; specifically low failure rate, large design margin, and short downtime for maintenance. A requirement that MTBF{>=}43 MTTR was derived as a necessary condition to achieve the required first wall/blanket availability, where MTBF is the mean time between failures and MTTR is the mean time to recover. Highlights of innovative and promising new concepts that may satisfy these criteria are provided. (orig.) 40 refs.

European development of He-cooled divertors for fusion power plants

International Nuclear Information System (INIS)

Norajitra, P.; Giniyatulin, R.; Kuznetsov, V.; Mazul, I.; Ovchinnikov, I.; Ihli, T.; Janeschitz, G.; Krauss, W.; Kruessmann, R.; Karditsas, P.; Maisonnier, D.; Sardain, P.; Nardi, C.; Papastergiou, S.; Pizzuto, A.

2005-01-01

Helium-cooled divertor concepts are considered suitable for use in fusion power plants for safety reasons, as they enable the use of a coolant compatible with any blanket concept, since water would not be acceptable e.g. in connection with ceramic breeder blankets using large amounts of beryllium. Moreover, they allow for a high coolant exit temperature for increasing the efficiency of the power conversion system. Within the framework of the European power plant conceptual study (PPCS), different helium-cooled divertor concepts based on different heat transfer mechanisms are being investigated at ENEA Frascati, Italy, and Forschungszentrum Karlsruhe, Germany. They are based on a modular design which helps reduce thermal stresses. The design goal is to withstand a high heat flux of about 10-15 MW/m 2 , a value which is considered relevant to future fusion power plants to be built after ITER. The development and optimisation of the divertor concepts require an iterative design approach with analyses, studies of materials and fabrication technologies, and the execution of experiments. These issues and the state of the art of divertor development shall be the subject of this report. (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.

Assessment of tritium breeding requirements for fusion power reactors

International Nuclear Information System (INIS)

Jung, J.

1983-12-01

This report presents an assessment of tritium-breeding requirements for fusion power reactors. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems in operation on a steady-state mode as well as on a pulsed mode. As an example, the UWMAK-I design was analyzed and it has been found that the startup inventory requirement calculated by the present method significantly differs from those previously calculated. The effect of reactor-parameter changes on the required tritium breeding ratio is also analyzed for a variety of reactor operation scenarios

New directions in fusion machines: report on the MFAC Panel X on high power density options

International Nuclear Information System (INIS)

Linford, R.K.

1985-01-01

The high cost of fusion is motivating a shift in research interest toward smaller, lower-cost systems. Panel X of the Magnetic Fusion Advisory Committee (MFAC) was charged to assess the potential benefits and problems associated with small, high-power-density approaches to fusion. The Panel identified figures of merit which are useful in evaluating various approaches to reduce the development costs and capital costs of fusion systems. As a result of their deliberations, the Panel recommended that ''...increased emphasis should be given to improving the mass power density of fusion systems, aiming at a minimum target of 100 kWe/tonne'', and that ''Increased emphasis should be given to concepts that offer the potential to reduce substantially the cost of development steps in physics and technology.''

Lawrence Livermore National Laboratory laser-fusion program

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1982-01-01

The goals of the Laser-Fusion Program at Lawrence Livermore National Laboratory are to produce well-diagnosed, high-gain, laser-driven fusion explosions in the laboratory and to exploit this capability for both military applications and for civilian energy production. In the past year we have made significant progress both theoretically and experimentally in our understanding of the laser interaction with both directly coupled and radiation-driven implosion targets and their implosion dynamics. We have made significant developments in fabricating the target structures. Data from the target experiments are producing important near-term physics results. We have also continued to develop attractive reactor concepts which illustrate ICF's potential as an energy producer

EMP Fusion

OpenAIRE

KUNTAY, Isık

2010-01-01

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

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

TOKMINA, Toroidal Magnetic Field Minimization for Tokamak Fusion Reactor. TOKMINA-2, Total Power for Tokamak Fusion Reactor

International Nuclear Information System (INIS)

Hatch, A.J.

1975-01-01

1 - Description of problem or function: TOKMINA finds the minimum magnetic field, Bm, required at the toroidal coil of a Tokamak type fusion reactor when the input is beta(ratio of plasma pressure to magnetic pressure), q(Kruskal-Shafranov plasma stability factor), and y(ratio of plasma radius to vacuum wall radius: rp/rw) and arrays of PT (total thermal power from both d-t and tritium breeding reactions), Pw (wall loading or power flux) and TB (thickness of blanket), following the method of Golovin, et al. TOKMINA2 finds the total power, PT, of such a fusion reactor, given a specified magnetic field, Bm, at the toroidal coil. 2 - Method of solution: TOKMINA: the aspect ratio(a) is minimized, giving a minimum value for Bm. TOKMINA2: a search is made for PT; the value of PT which minimizes Bm to the required value within 50 Gauss is chosen. 3 - Restrictions on the complexity of the problem: Input arrays presently are dimensioned at 20. This restriction can be overcome by changing a dimension card

Minimization of the external heating power by long fusion power rise-up time for self-ignition access in the helical reactor FFHR2m

International Nuclear Information System (INIS)

Mitarai, O.; Sagara, A.; Chikaraishi, H.; Imagawa, S.; Shishkin, A.A.; Motojima, O.

2006-10-01

Minimization of the external heating power to access self-ignition is advantageous to increase the reactor design flexibility and to reduce the capital and operating costs of the plasma heating device in a helical reactor. In this work we have discovered that a larger density limit leads to a smaller value of the required confinement enhancement factor, lower density limit margin reduces the external heating power, and over 300 s of the fusion power rise-up time makes it possible to reach a minimized heating power. While the fusion power rise-up time in a tokamak is limited by the OH transformer flux or the current drive capability, any fusion power rise-up time can be employed in a helical reactor for reducing the thermal stresses of the blanket and shields, because the confinement field is generated by the external helical coils. (author)

Magnetic fusion program in the United States: an overview and perspective

International Nuclear Information System (INIS)

Clarke, J.F.

1978-01-01

Continuing technical progress in magnetic fusion energy research and a coherent national program involving national laboratories, industry and universities has won strong support from the new Department of Energy. This review presents recent technical progress and examines fusion in relation to other long term energy supply options. Fusion is seen as a technology which, because of its apparently minimal environmental impacts and promise of reasonable cost, has a good chance of competing successfully with the other inexhaustible energy sources

Opportunities in the Fusion Energy Sciences Program. Appendix C: Topical Areas Characterization

Energy Technology Data Exchange (ETDEWEB)

None

1999-06-30

Recent years have brought dramatic advances in the scientific understanding of fusion plasmas and in the generation of fusion power in the laboratory. Today, there is little doubt that fusion energy production is feasible. The challenge is to make fusion energy practical. As a result of the advances of the last few years, there are now exciting opportunities to optimize fusion systems so that an attractive new energy source will be available when it may be needed in the middle of the next century. The risk of conflicts arising from energy shortages and supply cutoffs, as well as the risk of severe environmental impacts from existing methods of energy production, are among the reasons to pursue these opportunities.

Programs of the Materials and Radiation Effects Branch

International Nuclear Information System (INIS)

Dalder, E.N.C.

1976-01-01

This report describes specific efforts devoted to resolving fusion reactor materials needs as they relate to major fusion power program objectives and construction of major fusion facilities. Summaries of ERDA-sponsored research being conducted on the following areas are given: surface program, bulk irradiation program, dosimetry program, materials selection and development program, and neutron source development program

Safety and environmental aspects of deuterium--tritium fusion power plants: work shop summary

International Nuclear Information System (INIS)

1978-05-01

In September of 1977 a workshop was held on the safety and environmental aspects of fusion power plants to consider potential safety and environmental problems of fusion power plants and to reveal solutions or methods of solving those problems. The objective was to promote incorporation of safety and environmental protection into reactor design, thereby reducing the expense and delay of backfitting safety systems after reactor designs are complete. A dialogue was established between fusion reactor designers and safety and environmental researchers. Four topics, each with several subdivisions, were selected for discussion: radiation exposure, accidents, environmental effects, and plant safety. For each topic, discussion focused on the significance of the problem, and adequacy of current technology to solve the problem, design solutions available and research needed to solve the problem

Propagation of nuclear data uncertainties for fusion power measurements

Directory of Open Access Journals (Sweden)

Sjöstrand Henrik

2017-01-01

Full Text Available Neutron measurements using neutron activation systems are an essential part of the diagnostic system at large fusion machines such as JET and ITER. Nuclear data is used to infer the neutron yield. Consequently, high-quality nuclear data is essential for the proper determination of the neutron yield and fusion power. However, uncertainties due to nuclear data are not fully taken into account in uncertainty analysis for neutron yield calibrations using activation foils. This paper investigates the neutron yield uncertainty due to nuclear data using the so-called Total Monte Carlo Method. The work is performed using a detailed MCNP model of the JET fusion machine; the uncertainties due to the cross-sections and angular distributions in JET structural materials, as well as the activation cross-sections in the activation foils, are analysed. It is found that a significant contribution to the neutron yield uncertainty can come from uncertainties in the nuclear data.

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.

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

Chemistry in and from nuclear fusion

International Nuclear Information System (INIS)

Okamoto, M.

1989-01-01

The time, of the realization of nuclear fusion reactor is not clear even now. However, it is generally believed that the nuclear fusion is only one candidate of the big power source for humanbeing. We may be not able to, but our children or grandchildren would be able to see the nuclear fusion reactors. The nuclear fusion development may be the last and biggest technology program for us, so it will take so long leading time. Now, we are in the first stage of this leading time, I think. As being found in the history of every technology, chemistry is essential to develop the fusion nuclear technology. To assure the safety of the nuclear fusion system, chemistry should play the main role. There have been already not a few advanced chemistry initiated by the connected technologies with the nuclear fusion researches. The nuclear fusion needs chemistry and the nuclear fusion leads some of the new phases of chemistry. (author)

Preliminary proposal for a beryllium technology program for fusion applications

International Nuclear Information System (INIS)

1985-02-01

The program was designed to provide the answers to the critical issues of beryllium technology needed in fusion blanket designs. The four tasks are as follows: (1) Beryllium property measurements needed for fusion data base. (2) Beryllium stress relaxation and creep measurements for lifetime modelling calculations. (3) Simplified recycle technique development for irradiated beryllium. (4) Beryllium neutron multiplier measurements using manganese bath absolute calibration techniques

Technology spinoffs from the Magnetic Fusion Energy Program

International Nuclear Information System (INIS)

1984-02-01

This document briefly describes eight new spin-offs from the fusion program: (1) cray timesharing system, (2) CRT touch panel, (3) magneform, (4) plasma separation process, (5) homopolar resistance welding, (6) plasma diagnostic development, (7) electrodeless microwave lamp, and (8) superconducting energy storage

X-ray imaging in the laser-fusion program

International Nuclear Information System (INIS)

McCall, G.H.

1977-01-01

Imaging devices which are used or planned for x-ray imaging in the laser-fusion program are discussed. Resolution criteria are explained, and a suggestion is made for using the modulation transfer function as a uniform definition of resolution for these devices

Analysis of Confinement Strategies for a Tokamak Fusion Reactor

Energy Technology Data Exchange (ETDEWEB)

Girard, Christian; Gaillard, Jean-Philippe; Marbach, Gabriel; Cambi, Gilio; Cook, Ian; Johansson, Lise-Lotte; Meyder, Rainer; Mustoe, Julian; Pinna, Tonio

2001-01-15

The Safety and Environmental Assessment of Fusion Power (SEAFP) was performed in the framework of the European fusion program, whose results have already been published. The European Commission decided to continue this program for some identified issues that required development. One of these issues was the analysis and specification of the containment concepts that minimize accidental releases to the environment.To perform such an assessment, a methodology was followed to identify the most challenging accidental sequences in terms of containment integrity.The results of the accident selection and analysis that were performed during the extension of the SEAFP-2 program are given. Preliminary recommendations for the definition of a confinement strategy for tokamak fusion reactors are established.

Analysis of Confinement Strategies for a Tokamak Fusion Reactor

International Nuclear Information System (INIS)

Girard, Christian; Gaillard, Jean-Philippe; Marbach, Gabriel; Cambi, Gilio; Cook, Ian; Johansson, Lise-Lotte; Meyder, Rainer; Mustoe, Julian; Pinna, Tonio

2001-01-01

The Safety and Environmental Assessment of Fusion Power (SEAFP) was performed in the framework of the European fusion program, whose results have already been published. The European Commission decided to continue this program for some identified issues that required development. One of these issues was the analysis and specification of the containment concepts that minimize accidental releases to the environment.To perform such an assessment, a methodology was followed to identify the most challenging accidental sequences in terms of containment integrity.The results of the accident selection and analysis that were performed during the extension of the SEAFP-2 program are given. Preliminary recommendations for the definition of a confinement strategy for tokamak fusion reactors are established

New directions in fusion machines: report on the MFAC Panel X on high power density options

Energy Technology Data Exchange (ETDEWEB)

Linford, R.K.

1985-01-01

The high cost of fusion is motivating a shift in research interest toward smaller, lower-cost systems. Panel X of the Magnetic Fusion Advisory Committee (MFAC) was charged to assess the potential benefits and problems associated with small, high-power-density approaches to fusion. The Panel identified figures of merit which are useful in evaluating various approaches to reduce the development costs and capital costs of fusion systems. As a result of their deliberations, the Panel recommended that ''...increased emphasis should be given to improving the mass power density of fusion systems, aiming at a minimum target of 100 kWe/tonne'', and that ''Increased emphasis should be given to concepts that offer the potential to reduce substantially the cost of development steps in physics and technology.''

OSIRIS and SOMBRERO Inertial Fusion Power Plant Designs, Volume 2: Designs, Assessments, and Comparisons

Energy Technology Data Exchange (ETDEWEB)

Meier, W. R.; Bieri, R. L.; Monsler, M. J.; Hendricks, C. D.; Laybourne, P.; Shillito, K. R.

1992-03-01

This is a comprehensive design study of two Inertial Fusion Energy (IFE) electric power plants. Conceptual designs are presented for a fusion reactor (called Osiris) using an induction-linac heavy-ion beam driver, and another (called SOMBRERO) using a KrF laser driver. The designs covered all aspects of IFE power plants, including the chambers, heat transport and power conversion systems, balance-of-plant facilities, target fabrication, target injection and tracking, as well as the heavy-ion and KrF drivers. The point designs were assessed and compared in terms of their environmental & safety aspects, reliability and availability, economics, and technology development needs.

International ITER fusion energy organization. Paving the way to power generation from nuclear fusion

International Nuclear Information System (INIS)

Preuschen-Liebenstein, R. von

2006-01-01

ITER (Latin: the way) is the acronym of a new international large research facility gradually taking shape after the meeting of Gorbachev and Reagan in Reykjavik in 1985. Under the auspices of the IAEA, worldwide scientific and industrial cooperation with 'home teams' of each of the ITER partners began at that time which were commissioned to accumulate the knowledge and the technology of nuclear fusion in the participating countries. At the end of the preparation and decisionmaking process, the design draft of the ITER reactor was elaborated in international cooperation as the basis of the ITER Convention. After lengthy negotiations among the international ITER partners, a European site for the ITER organization and its reactor was found at Cadarache, France. As the first ITER member, Europe now initiated worldwide cooperation in research and development, seeking to demonstrate the technical and scientific feasibility of tapping fusion power for peaceful purposes. The Council of the European Union (competitiveness), at its meeting on September 25, 2006, decided to sign the ITER Convention about the establishment of the International ITER Fusion Energy Organization ('ITER Organization') and about the mutual obligation to make the necessary contributions towards the construction of ITER. (orig.)

Maryland controlled fusion research program. Volume I

International Nuclear Information System (INIS)

1985-01-01

This renewal proposal describes the University of Maryland research program on Magnetic Fusion Energy for a three-year period beginning January 1, 1986. This program consists of five tasks: (I) Plasma Theory; (II) Electron Cyclotron Emission Diagnostics for Mirror Machines; (III) Electron Cyclotron Emission Diagnostics on TFTR; (IV) Atomic Physics; and (V) Magnetic Field Measurement by Ion Beams. The four separate tasks of continuing research (Tasks I to IV) and the new experimental task (Task V) are described in detail. The task descriptions contain estimated budgets for CY 86, 87, and 88

Overview of international fusion technology programs

International Nuclear Information System (INIS)

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

1979-01-01

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

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.

Background information and technical basis for assessment of environmental implications of magnetic fusion energy

International Nuclear Information System (INIS)

Cannon, J.B.

1983-08-01

This report contains background information for assessing the potential environmental implications of fusion-based central electric power stations. It was developed as part of an environmental review of the Magnetic Fusion Energy Program. Transition of the program from demonstration of purely scientific feasibility (breakeven conditions) to exploration of engineering feasibility suggests that formal program environmental review under the National Environmental Policy Act is timely. This report is the principal reference upon which an environmental impact statement on magnetic fusion will be based

Alternate applications of fusion power: development of a high-temperature blanket for synthetic-fuel production

International Nuclear Information System (INIS)

Howard, P.A.; Mattas, R.F.; Krajcinovic, D.; DePaz, J.; Gohar, Y.

1981-11-01

This study has shown that utilization of the unique features of a fusion reactor can result in a novel and potentially economical method of decomposing steam into hydrogen and oxygen. Most of the power of fusion reactors is in the form of energetic neutrons. If this power could be used to produce high temperature uncontaminated steam, a large fraction of the energy needed to decomposee the steam could be supplied as thermal energy by the fusion reaction. Proposed high temperature electrolysis processes require steam temperature in excess of 1000 0 C for high efficiency. The design put forth in this study details a system that can accomplish that end

ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT. ANNUAL REPORT TO THE US DEPARTMENT OF ENERGY

International Nuclear Information System (INIS)

PROJECT STAFF

2001-01-01

OAK A271 ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT ANNUAL REPORT TO THE US DEPARTMENT OF ENERGY. The General Atomics (GA) Advanced Fusion Technology Program seeks to advance the knowledge base needed for next-generation fusion experiments, and ultimately for an economical and environmentally attractive fusion energy source. To achieve this objective, they carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. The technology development activities take full advantage of the GA DIII-D program, the DIII-D facility and the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility

Conceptual design of a laser fusion power plant. Part I. An integrated facility

International Nuclear Information System (INIS)

1981-07-01

This study is a new preliminary conceptual design and economic analysis of an inertial confinement fusion (ICF) power plant performed by Bechtel under the direction of Lawrence Livermore National Laboratory (LLNL). The purpose of a new conceptual design is to examine alternatives to the LLNL HYLIFE power plant and to incorporate information from the recent liquid metal cooled power plant conceptual design study (CDS) into the reactor system and balance of plant design. A key issue in the design of a laser fusion power plant is the degree of symmetry in the illumination of the target that will be required for a proper burn. Because this matter is expected to remain unresolved for some time, another purpose of this study is to determine the effect of symmetry requirements on the total plant size, layout, and cost

Update of ZTH physics and design issues and physics goals of ZTH and role in the Fusion Program

International Nuclear Information System (INIS)

DiMarco, J.N.

1990-01-01

The ZTH construction program is scheduled for completion in December of 1992. Some design features are still amenable to changes directed by new physics or computational information. Numerical results for the ZTH tapered poloidal field gap show that a relatively simple linear taper results in substantial reduction in field error. This design is simpler to manufacture compared with the compound curve predicted by analytical calculations. Also, ongoing analysis of ZT-40M data indicates that the fluctuation levels of magnetic fields and x-rays at high θ (1.7), can be reduced to the fluctuation levels at ''standard'' operational θ (1.4) by changing the winding configuration of the toroidal field (TF) coils. The effect is thought to depend on the shell-like action of the TF coils when they consist of many turns in parallel. Magnetic-field effects, such as field errors, at the unshielded toroidal-field butt-joint gap in the shell can be reduced by this effective external shell. Design implications for installing a second low-current TF coil on ZTH are presented. ZTH has the capability of operating at 4 MA with the addition of power supplies. The projected parameters of ZTH are discussed in the context of various conceptual design. The sensitivity of the conceptual design to the physics results from machines like RFX and ZTH is reviewed. It is shown that the 4 MA ZTH physics results will make a significant advance for the RFP program toward the programmatic RFP fusion goals. Finally, the influence of RFP and tokamak physics on the conceptual design of high mass-power-density (MPD) fusion reactors is investigated through the TITAN and ARIES studies. The confinement characteristics required of these conceptual designs are compared; physics issues are identified that are required to bring the MPD and fusion-power-core of the tokamak designs into coincidence with the RFP designs

Laser requirements for a laser fusion energy power plant

Institute of Scientific and Technical Information of China (English)

Stephen; E.Bodner; Andrew; J.Schmitt; John; D.Sethian

2013-01-01

We will review some of the requirements for a laser that would be used with a laser fusion energy power plant, including frequency, spatial beam smoothing, bandwidth, temporal pulse shaping, efficiency, repetition rate, and reliability. The lowest risk and optimum approach uses a krypton fluoride gas laser. A diode-pumped solid-state laser is a possible contender.

Nuclear fusion and neutron processes

International Nuclear Information System (INIS)

Orlov, V.V.; Shatalov, G.E.; Sherstnev, K.E.

1984-01-01

Problems of providing development of the design of an experimental fusion reactor with necessary neutron-physical data are discussed. Isotope composition of spent fuel in the blanket of a hybride fusion reactor (HFR) is given. Neutron balance of the reactor with Li-blanket and neutron balance of the reactor with Pb-multiplier are disclosed. A simplified scheme of neutron and energy balance in the HFR blanket is given. Development and construction of the experimental power reactor is shown to become the nearest problem of the UTS program. Alongside with other complex physical and technical problems solution of this problem requires realization of a wide program of neutron-physical investigations including measurements with required accuracy of neutron cross sections, development of methodical, program and constant basis of neutron calculations and macroscopic experiments on neutron sources

Lasers and particle beam for fusion and strategic defense

International Nuclear Information System (INIS)

Anon.

1986-01-01

This special issue of the Journal of Fusion Energy consists of the edited transscripts of a symposium on the applications of laser and particle beams to fusion and strategic defense. Its eleven papers discuss these topics: the Strategic Defense Initiative; accelerators for heavy ion fusion; rf accelerators for fusion and strategic defense; Pulsed power, ICF, and the Strategic Defense Initiative; chemical lasers; the feasibility of KrF lasers for fusion; the damage resistance of coated optic; liquid crystal devices for laser systems; fusion neutral-particle beam research and its contribution to the Star Wars program; and induction linacs and free electron laser amplifiers for ICF devices and directed-energy weapons

ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT. ANNUAL REPORT TO THE U.S. DEPARTMENT OF ENERGY OCTOBER 1, 2001 THROUGH SEPTEMBER 30, 2002

International Nuclear Information System (INIS)

PROJECT STAFF

2003-01-01

OAK-B135 The General Atomics (GA) Advanced Fusion Technology program seeks to advance the knowledge base needed for next-generation fusion experiments and, ultimately, for an economical and environmentally attractive fusion energy source. To achieve this objective, we carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and we conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. Our technology development activities take full advantage of the GA DIII-D program, the DIII-D facility and the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility. The following sections summarize GA's FY02 work in the areas of Fusion Power Plant Studies (ARIES, Section 2), Inertial Fusion Energy (IFE) Chamber Analysis (Section 3), IFE Target Supply System Development (Section 4), Next Step Fusion Design (Section 5), Advanced Liquid Plasma Facing Surfaces (ALPS, Section 6), Advanced Power Extraction Study (APEX, Section 7), Plasma Interactive Materials (DiMES, Section 8) and RF Technology (Section 9). Our work in these areas continues to address many of the issues that must be resolved for the successful construction and operation of next-generation experiments and, ultimately, the development of safe, reliable, economic fusion power plants

Progress on the European Safety and Environmental Assessment of Fusion Power (SEAFP)

International Nuclear Information System (INIS)

Cook, I.

1994-01-01

The Safety and Environmental Assessment of Fusion Power (SEAFP) project was set up by the European Community Fusion Programme in response to recommendations made by a high level Fusion Programme Evaluation Board. The Evaluation Board stated that fusion potentially possesses ''inherent environmental and safety advantages over all current alternatives for base load electricity generation'', but that a ''convincing demonstration'' of these potential advantages is necessary. SEAFP is undertaken by three main participants: the NET Team, The Euratom/UKAEA Association, and European industry. Other EC fusion laboratories also participate. The work embraces the outline design of fusion power stations, the safety and environmental assessment of those designs, and interactions between design and assessment to improve the design. The project began in April 1992 and will report in December 1994. In the first year of the project, five candidate blanket concepts were developed in parallel. Other aspects of design were developed as far as possible independently of the blanket designs. Assessments were made of the technical merits of the candidate designs, and scoping calculations were used to provide preliminary assessments of their accident and waste management characteristics. Accident identification studies were used to select the bounding sequences to be analysed later in detail. Targets for safety and environmental performance were developed. This phase of the study culminated, in August 1993, in the selection of two plant models, one based on a water/martensitic steel/lithium-lead blanket, the other based on a helium/vanadium alloy/lithium oxide blanket, to be developed and assessed in more detail. Other design variants will be assessed through sensitivity studies. ((orig.))

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.)

A proposal of nuclear fusion power plant equipped with SMES