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Stellarators. Present Status and Future Planning
STELLARATORS Present Status and Future Planning H. Wobig, Garching IMax-Planck-Institut für Plasmaphysikl magnetic axis Fig. 1 — Period of toroidally dosed magnetic surfaces. The stellarator is a closed toroidal device open-ended configurations like mirror ma designed to confine a hot plasma In a ma chines (see EN, 12 8/9) there are always gnetic field. It is one of the oldest concepts plasma particles which escape the confine magnetic surfaces is investigated by field to have been investigated in the search for ment volume along the magnetic field and line integration. The topology of the field controlled thermonuclear fusion. an isotropic distribution function cannot be lines is determined by the rotational trans The basic idea of the stellarator was maintained. If this anisotropy is too strong form or twist number 1/27t (or+), which is developed by Lyman Spitzer, Professor of it gives rise to instabilities and enhanced the number of revolutions of a field line Astronomy at Princeton in 19511). Experi plasma losses. It is mainly to avoid these around the magnetic axis during one toroi mental studies began in 1952 and after the disadvantages that toroidal confinement dal revolution. declassification of fusion research in 1958 has been preferred. The need for a helical field can be under the idea was picked up by other research In toroidal configurations, the currents stood from a look at the particle orbits. groups. In Europe, the first stellarators which generate the confining magnetic Charged particles tend to follow the field were built in the Max-Planck Institute for fields can be classified under three lines and unless these are helical, because Physics and Astrophysics in Munich and categories : of inhomogeneities, the particles will drift later at Culham, Moscow and Karkhov. -
Assessment of DEMO Reactors for Fusion Power Utilization
九州大学学術情報リポジトリ Kyushu University Institutional Repository Assessment of DEMO Reactors for Fusion Power Utilization Elserafy, Hatem Interdisciplinary Graduate school of Engineering Sciences, Kyushu University https://doi.org/10.5109/2174854 出版情報：Evergreen. 5 (4), pp.18-25, 2018-12. Green Asia Education Center バージョン：published 権利関係： EVERGREEN Joint Journal of Novel Carbon Resource Sciences & Green Asia Strategy, Vol. 05, Issue 04, pp.18-25, December 2018 (Review Article) Assessment of DEMO Reactors for Fusion Power Utilization Hatem Elserafy Interdisciplinary Graduate school of Engineering Sciences, Kyushu University, Japan *Author to whom correspondence should be addressed, E-mail: [email protected] (Received November 15, 2018; accepted December 27, 2018). Given the undeniable climate change caused by global warming, decreasing the carbon footprint by using alternative energy sources became necessary. Thermonuclear fusion energy is one of the strongest candidates when it comes to alternative energy sources since it is safe, has negligible carbon footprint and its yield is incomparable to any other alternative. Credential as fusion performance may be; feasibility and economic attractiveness are something to be considered. The next stage fusion reactors are called DEMOnstration (DEMO) and are being assessed by various sources in terms of performance. In this work, DEMO fusion reactors are to be reviewed and their specifications are to be analyzed in terms of feasibility, while demonstrating how the tritium fueling stage not only presents a challenge for calculating fusion power costs, but also that fusion energy requires further R&D before it can be integrated into the power grid. Keywords: thermonuclear fusion, DEMO, TBR. 1. Introduction thought of as the most promising unexploited energy source [6]. -
Iter: Os Caminhos Da Energia De Fusão E O Brasil (2015)
ITER Os caminhos da energia de fusão e o Brasil MINISTÉRIO DAS RELAÇÕES EXTERIORES Ministro de Estado Embaixador Mauro Luiz Iecker Vieira Secretário -Geral Embaixador Sérgio França Danese FUNDAÇÃO ALEXANDRE DE GUSMÃO Presidente Embaixador Sérgio Eduardo Moreira Lima Instituto de Pesquisa de Relações Internacionais Diretor Embaixador José Humberto de Brito Cruz Centro de História e Documentação Diplomática Diretor Embaixador Maurício E. Cortes Costa Conselho Editorial da Fundação Alexandre de Gusmão Presidente Embaixador Sérgio Eduardo Moreira Lima Membros Embaixador Ronaldo Mota Sardenberg Embaixador Jorio Dauster Magalhães e Silva Embaixador Gonçalo de Barros Carvalho e Mello Mourão Embaixador José Humberto de Brito Cruz Embaixador Julio Glinternick Bitelli Ministro Luís Felipe Silvério Fortuna Professor Francisco Fernando Monteoliva Doratioto Professor José Flávio Sombra Saraiva Professor Eiiti Sato A Fundação Alexandre de Gusmão, instituída em 1971, é uma fundação pública vinculada ao Ministério das Relações Exteriores e tem a finalidade de levar à sociedade civil informações sobre a realidade internacional e sobre aspectos da pauta diplomática brasileira. Sua missão é promover a sensibilização da opinião pública nacional para os temas de relações internacionais e para a política externa brasileira. Augusto Pestana ITER Os caminhos da energia de fusão e o Brasil Brasília, 2015 Direitos de publicação reservados à Fundação Alexandre de Gusmão Ministério das Relações Exteriores Esplanada dos Ministérios, Bloco H Anexo II, Térreo 70170 ‑900 Brasília–DF Telefones:(61) 2030 ‑6033/6034 Fax:(61) 2030 ‑9125 Site: www.funag.gov.br E ‑mail: [email protected] Equipe Técnica: Eliane Miranda Paiva Fernanda Antunes Siqueira Gabriela Del Rio de Rezende Luiz Antônio Gusmão André Luiz Ventura Ferreira Projeto Gráfico e Capa: Yanderson Rodrigues Programação Visual e Diagramação: Gráfica e Editora Ideal Impresso no Brasil 2015 P476 Pestana, Augusto. -
LANL Fusion Capabilities
LANL Fusion Capabilities INFUSE workshop Jan 22-23, 2019 1 Managed by Triad National Security, LLC for the U.S. Department of Energy’s NNSA Los Alamos has a long history of fusion research James Tuck, Ivy Mike, 1952 Perhapsatron, 1953 • Today magnetic and inertial fusion work resides in the Physics Division, Theory Division, and X Division (Weapons). There are also related capabilities in detectors, radiation damage, and tritium handling. • Dr. John Kline ( [email protected] ) is the present Fusion Energy Sciences (and Inertial Fusion) program manager, and a point-of-contact. 2 Managed by Triad National Security, LLC for the U.S. Department of Energy’s NNSA 3 Managed by Triad National Security, LLC for the U.S. Department of Energy’s NNSA FRC’s were developed in Russia and Los Alamos FRC’s are high beta plasmas, with many interesting features 4 Managed by Triad National Security, LLC for the U.S. Department of Energy’s NNSA Today FRC plasmas are still being explored 5 Managed by Triad National Security, LLC for the U.S. Department of Energy’s NNSA Magnetized Plasma Team in P-24 Plasma Physics We do experimental plasma work for FES, APRA-E, and NNSA sponsors, with national and international partners, including small businesses. We use our knowledge of plasma diagnostics, pulsed power expertise, and HED plasmas in the areas of fusion energy, weapons support, and basic plasma science. Team Leader: Glen Wurden ([email protected]) Staff: Hsu, Weber, Langendorf, Dunn, Shimada Postdocs: Tom Byvank, Kevin Yates, John Boguski Student: Chris Roper (Summer) 6 Managed by Triad National Security, LLC for the U.S. -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
SCIENCE and INNOVATION at Los Alamos
SCIENCE AND INNOVATION at Los Alamos Los Alamos Science Number 21 1993 1993 Number 21 Los Alamos Science 1 . Fred Reines (left) helps lower Wright Langham into a detector similar to the one used by Reines to detect neutrinos for the first time. The active medium of the detector was a liquid scintillator developed by F. Newton Hayes for assays of large biological sam- ples. The availability of liquid scintillators led to the whole-body counter, a device for monitoring the amount of certain radionu- clides in the bodies of workers exposed to radioactive materials. Wright Langham was one of the world’s experts on the metabo- lism of plutonium. Lattice-gas hydrodynamics, a discrete model for fluid flow, was invented by Brosl Hasslacher at Los Alamos with U. Frisch and Y. Pomeau. This novel formulation provides a fast, efficient, reliable method for simulating the Navier-Stokes equations and two-phase flow. A modification by Ken Eggert and coworkers is now being applied to model flow through porous media, a problem of great interest to oil companies. Norman Doggett and Judy Tesmer examine a gel at the Laboratory’s Center for Human Genome Studies. The Human Genome Project, a joint DOE-NIH effort, was largely conceived at a DOE meeting in Santa Fe in 1986. Researchers at the Los Alamos Center developed a widely used technique for fingerprinting DNA, discovered the human telomere (the se- quence at the ends of every human chromosome), are developing physical maps of several human chromosomes, and are preparing chromosome-specific libraries of clones, which are extremely useful in physical-mapping projects. -
Fast Track Concept in the European Fusion Programme
JP0250524 JAERI-Conf 2002-010 IV. FAST TRACK CONCEPT IN THE EUROPEAN FUSION PROGRAMME Prof. Harald Bolt Director of Materials Research Division, Max-Planck-Institute for Plasma Physics Abstract Recently an expert meeting regarding a possible acceleration of the fusion programme with a view to energy production ("fast track") was held on the initiative of the EU Research Council. In the course of the discussions about the fast track programme, it has turned out that successful extraction of reactor grade heat and tritium from the blanket modules is essential in the ITER operation. In parallel with ITER, material development using a high intensity neutron source is essential to establish a database for licensing. The operation of a reactor combining DEMO and PROTO generations into a single step could be around 2030. 1. Introduction A reference roadmap has been discussed which leads from ITER to DEMO and PROTO fusion reactors in EU. Among these discussions, the significant role of fusion reactors as electrical power resources and their timely availability to society has been emphasized. From this view point, it has been proposed to demonstrate the feasibility of fusion energy within 20-30 years, the so called "fast track" programme. This means that demonstration of fusion energy will be in 2030, not in 2050 which was a conventional fusion program so fat. In the line with this scope, the Fast Track Working Group was rganized by the EU Research Council in November 2001, and reported the first assessment of the fast track schedule. In this paper, the main results of the working group are described as well as the materials development program which has to be carried out acc ordingly. -
A European Success Story the Joint European Torus
EFDA JET JETJETJET LEAD ING DEVICE FOR FUSION STUDIES HOLDER OF THE WORLD RECORD OF FUSION POWER PRODUCTION EXPERIMENTS STRONGLY FOCUSSED ON THE PREPARATION FOR ITER EXPERIMENTAL DEVICE USED UNDER THE EUROPEAN FUSION DEVELOPEMENT AGREEMENT THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY EFDA Fusion: the Energy of the Sun If the temperature of a gas is raised above 10,000 °C virtually all of the atoms become ionised and electrons separate from their nuclei. The result is a complete mix of electrons and ions with the sum of all charges being very close to zero as only small charge imbalance is allowed. Thus, the ionised gas remains almost neutral throughout. This constitutes a fourth state of matter called plasma, with a wide range of unique features. D Deuterium 3He Helium 3 The sun, and similar stars, are sphe- Fusion D T Tritium res of plasma composed mainly of Li Lithium hydrogen. The high temperature, 4He Helium 4 3He Energy U Uranium around 15 million °C, is necessary released for the pressure of the plasma to in Fusion T balance the inward gravitational for- ces. Under these conditions it is pos- Li Fission sible for hydrogen nuclei to fuse together and release energy. Nuclear binding energy In a terrestrial system the aim is to 4He U produce the ‘easiest’ fusion reaction Energy released using deuterium and tritium. Even in fission then the rate of fusion reactions becomes large enough only at high JG97.362/4c Atomic mass particle energy. Therefore, when the Dn required nuclear reactions result from the thermal motions of the nuclei, so-called thermonuclear fusion, it is necessary to achieve u • extremely high temperatures, of at least 100 million °C. -
Operational Characteristics of the Stabilized Toroidal Pinch Machine, Perhapsatron S-4
P/2488 USA Operational Characteristics of the Stabilized Toroidal Pinch Machine, Perhapsatron S-4 By J. P. Conner, D. C. H age r m an, J. L. Honsaker, H. J. Karr, J. P. Mize, J. E. Osher, J. A. Phillips and E. J. Stovall Jr. Several investigators1"6 have reported initial success largely inductance-limited and not resistance-limited in stabilizing a pinched discharge through the utiliza- as observed in PS-3. After gas breakdown about 80% tion of an axial Bz magnetic field and conducting of the condenser voltage appears around the secondary, walls, and theoretical work,7"11 with simplifying in agreement with the ratio of source and load induct- assumptions, predicts stabilization under these con- ances. The rate of increase of gas current is at first ditions. At Los Alamos this approach has been large, ~1.3xlOn amp/sec, until the gas current examined in linear (Columbus) and toroidal (Per- contracts to cause an increase in inductance, at which hapsatron) geometries. time the gas current is a good approximation to a sine Perhapsatron S-3 (PS-3), described elsewhere,4 was curve. The gas current maximum is found to rise found to be resistance-limited in that the discharge linearly with primary voltage (Fig. 3), deviating as current did not increase significantly for primary expected at the higher voltages because of saturation vçltages over 12 kv (120 volts/cm). The minor inside of the iron core. diameter of this machine was small, 5.3 cm, and the At the discharge current maximum, the secondary onset of impurity light from wall material in the voltage is not zero, and if one assumes that there is discharge occurred early in the gas current cycle. -
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey
The Stellarator Program J. L, Johnson, Plasma Physics Laboratory, Princeton University, Princeton, New Jersey, U.S.A. (On loan from Westlnghouse Research and Development Center) G. Grieger, Max Planck Institut fur Plasmaphyslk, Garching bel Mun<:hen, West Germany D. J. Lees, U.K.A.E.A. Culham Laboratory, Abingdon, Oxfordshire, England M. S. Rablnovich, P. N. Lebedev Physics Institute, U.S.3.R. Academy of Sciences, Moscow, U.S.S.R. J. L. Shohet, Torsatron-Stellarator Laboratory, University of Wisconsin, Madison, Wisconsin, U.S.A. and X. Uo, Plasma Physics Laboratory Kyoto University, Gokasho, Uj', Japan Abstract The woHlwide development of stellnrator research is reviewed briefly and informally. I OISCLAIWCH _— . vi'Tli^liW r.'r -?- A stellarator is a closed steady-state toroidal device for cer.flning a hot plasma In a magnetic field where the rotational transform Is produced externally, from torsion or colls outside the plasma. This concept was one of the first approaches proposed for obtaining a controlled thsrtnonuclear device. It was suggested and developed at Princeton in the 1950*s. Worldwide efforts were undertaken in the 1960's. The United States stellarator commitment became very small In the 19/0's, but recent progress, especially at Carchlng ;ind Kyoto, loeethar with «ome new insights for attacking hotii theoretics] Issues and engineering concerns have led to a renewed optimism and interest a:; we enter the lQRO's. The stellarator concept was borr In 1951. Legend has it that Lyman Spiczer, Professor of Astronomy at Princeton, read reports of a successful demonstration of controlled thermonuclear fusion by R. -
Highlights in Early Stellarator Research at Princeton
J. Plasma Fusion Res. SERIES, Vol.1 (1998) 3-8 Highlights in Early Stellarator Research at Princeton STIX Thomas H. Department of Astrophysical Sciences, Princeton University, Princeton, NJ 08540, USA (Received: 30 September 1997/Accepted: 22 October 1997) Abstract This paper presents an overview of the work on Stellarators in Princeton during the first fifteen years. Particular emphasis is given to the pioneering contributions of the late Lyman Spitzer, Jr. The concepts discussed will include equilibrium, stability, ohmic and radiofrequency plasma heating, plasma purity, and the problems associated with creating a full-scale fusion power plant. Brief descriptions are given of the early Princeton Stellarators: Model A, Model B, Model B-2, Model B-3, Models 8-64 and 8-65, and Model C, and also of the postulated fusion power plant, Model D. Keywords: Spitzer, Kruskal, stellarator, rotational transform, Bohm diffusion, ohmic heating, magnetic pumping, ion cyclotron resonance heating (ICRH), magnetic island, tokamak On March 31 of this year, at the age of 82, Lyman stellarator was brought to the headquarters of the U.S. Spitzer, Jr., a true pioneer in the fields of astrophysics Atomic Energy Commission in Washington where it re- and plasma physics, died. I wish to dedicate this presen- ceived a favorable reception. Spitzer chose the name tation to his memory. "Project Matterhorn" for the project which was to be Forty-six years ago, in early 1951, Spitzer, then sited in the Princeton area, on the newly acquired For- chair of the Department of Astronomy at Princeton restal tract, and funding began on July 1 of that year University, together with Princeton physicist John 121- Wheeler, had been thinking about the physics of ther- Spitzer's earliest stellarator papers comprise a truly monoclear processes. -
Pulsed Power Science and Engineering
Department of Energy National Nuclear Security Administration Laboratory Residency Graduate Fellowship (DOE NNSA LRGF) Residency Opportunities at Lawrence Livermore National Laboratory Lawrence Livermore National Laboratory (LLNL) pairs multidisciplinary science and engineering with world-class experimental and computing resources to develop technical solutions to the most pressing national security problems of our time. Livermore's defining responsibility is ensuring the safety, security and reliability of the nation's nuclear deterrent without nuclear testing. As part of the Stockpile Stewardship Program, LLNL researchers are tackling the grand challenge of understanding the scientific details of nuclear weapons performance through nonnuclear tests and experimentally validated computer simulations. LLNL's national security mission is broader than stockpile stewardship, as dangers from nuclear proliferation and terrorism to energy shortages and climate change threaten both national security and global stability. Livermore's multidisciplinary science and engineering are being applied to achieve breakthroughs for counterterrorism and nonproliferation, defense and intelligence, domestic security and energy and environmental security. Lawrence Livermore offers fellowship opportunities in the following research areas: Pulsed power science and engineering Pulsed power is a critical technology at LLNL, supporting a broad range of applications relating to national security and fundamental science. The pulsed power systems at LLNL range from low-energy ultra-fast pulsers used in diagnostic systems, to explosively-driven flux compression generators, to the 400 million joule pulsed power driver for the National Ignition Facility (NIF) - the world’s largest laser system. For more than 50 years LLNL researchers have been actively researching, developing, designing, instrumenting and executing experiments on pulsed power systems for multiple programs to support high-energy-density physics experiments in support of the U.S.