WorldWideScience

Sample records for beam fusion research

  1. Progress in light ion beam fusion research on PBFA II

    International Nuclear Information System (INIS)

    PBFA II is a 100 TW pulsed power accelerator constructed at Sandia National Laboratories for use in the Light Ion Fusion Program. The objective of PBFA II is to accelerate and focus upon an inertial confinement fusion (ICF) target a lithium beam with sufficient energy, power, and power density to perform ignition scaling experiments. The technologies used in PBFA II include: (1) primary energy storage and compression with 6 MV, low-inductance Marx generators, (2) pulse forming in water-insulated, water-dielectric lines with self-closing water switches, (4) voltage addition in vacuum using self-magnetically-insulated biconic transmission lines, (5) inductive energy storage and pulse compression using a fast-opening plasma erosion switch, (6) beam formation using a magnetically-insulated ion diode, and (7) space-charge and current-neutralized beam propagation to the target in a gas-filled cell. The first multimodule shot was on December 11, 1985. The plans for PBFA II include development and demonstration of the pulse-shaping techniques which are necessary for high-gain target compressions. Following a modification of the accelerator which will probably include an ''extraction'' ion diode, a 4- to 5-meter plasma channel for beam bunching during propagation, and a target chamber located beneath the accelerator, temporally-shaped ion beam pulses will be available for pulse-shaped target experiments. (author)

  2. Light ion beam fusion research at ILE, Osaka University

    International Nuclear Information System (INIS)

    To achieve a cannonball target implosion with a focused power density of 1014 W/cm2, the authors have proposed a two-stage charge stripping ion diode as light ion beam inertial confinement fusion driver and developed an induction voltage adder, Reiden-SHVS (4 MV, 40 kA, 100 ns). A ramped voltage waveform from 1.5 MW to 3.2 MV during 70 ns was successfully generated by transit time control between pulse line and induction cavities. Beam bunching experiments with ramped voltage were performed by using a carbon plasma injection ion source (up to 400 A/cm2), which offered a first turn-on ion source without neutrals. The rise time of the carbon beam current became approximately half its value during 25 cm of flight path, because of bunching. In two-stage diode experiments, the second diode was operated as an ion beam injected diode. The ion current density measured behind the second diode was several times the simple Child-Langmuir value. The results indicate the formation of a virtual anode in the ion beam injected diode. A two-stage charge stripping diode was demonstrated. A plastic stripping foil was located between the two diodes. The spectrum and charge states of the carbon ions were in agreement with a calculation where the effects of charge stripping and recombination in the stripping foil were included. The experimental results showed that the multistage diode is promising, by accelerating ions to higher energies, as a driver of inertial confinement fusion. (author). 9 refs, 6 figs

  3. Automatic calibration and signal switching system for the particle beam fusion research data acquisition facility

    International Nuclear Information System (INIS)

    This report describes both the hardware and software components of an automatic calibration and signal system (Autocal) for the data acquisition system for the Sandia particle beam fusion research accelerators Hydra, Proto I, and Proto II. The Autocal hardware consists of off-the-shelf commercial equipment. The various hardware components, special modifications and overall system configuration are described. Special software has been developed to support the Autocal hardware. Software operation and maintenance are described

  4. Particle beam fusion progress report January 1979 through June 1979

    International Nuclear Information System (INIS)

    The following chapters are included: (1) fusion target studies, (2) target experiments, (3) particle beam source development, (4) particle beam experiments, (5) pulsed power research and development, (6) pulsed fusion applications, and (7) electron beam fusion accelerator project

  5. Accelerator and fusion research division

    International Nuclear Information System (INIS)

    This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations

  6. U.S. Heavy Ion Beam Research for High Energy Density Physics Applications and Fusion

    International Nuclear Information System (INIS)

    Key scientific results from recent experiments, modeling tools, and heavy ion accelerator research are summarized that explore ways to investigate the properties of high energy density matter in heavy-ion-driven targets, in particular, strongly-coupled plasmas at 0.01 to 0.1 times solid density for studies of warm dense matter, which is a frontier area in high energy density physics. Pursuit of these near-term objectives has resulted in many innovations that will ultimately benefit heavy ion inertial fusion energy. These include: neutralized ion beam compression and focusing, which hold the promise of greatly improving the stage between the accelerator and the target chamber in a fusion power plant; and the Pulse Line Ion Accelerator (PLIA), which may lead to compact, low-cost modular linac drivers

  7. US heavy ion beam research for high energy density physics applications and fusion

    International Nuclear Information System (INIS)

    Key scientific results from recent experiments, modeling tools, and heavy ion accelerator research are summarized that explore ways to investigate the properties of high energy density matter in heavy-ion-driven targets, in particular, strongly-coupled plasmas at 0.01 to 0.1 times solid density for studies of warm dense matter, which is a frontier area in high energy density physics. Pursuit of these near-term objectives has resulted in many innovations that will ultimately benefit heavy ion inertial fusion energy. These include: neutralized ion beam compression and focusing, which hold the promise of greatly improving the stage between the accelerator and the target chamber in a fusion power plant; and the Pulse Line Ion Accelerator (PLIA), which may lead to compact, low-cost modular linac drivers. (authors)

  8. Fusion research in Hungary

    International Nuclear Information System (INIS)

    Hungarian fusion research started in the 1970s, when the idea of installing a small tokamak experiment emerged. In return to computer equipment a soviet tokamak was indeed sent to Hungary and started to operate as MT-1 at the Central Research Institute for Physics (KFKI) in 1979. Major research topics included diagnostic development, edge plasma studies and investigation of disruptions. Following a major upgrade in 1992 (new vacuum vessel, active position control and PC network based data acquisition system) the MT-1M tokamak was used for the study of transport processes with trace impurity injection, micropellet ablation studies, X-ray tomography and laser blow-off diagnostic development. Although funding ceased in the middle of the 90's the group was held alive by collaborations with EU fusion labs: FZ -Juelich, IPP-Garching and CRPP-EPFL Lausanne. In 1998 the machine was dismantled due to reorganization of the Hungarian Academy of Sciences. New horizons opened to fusion research from 1999, when Hungary joined EURATOM and a fusion Association was formed. Since then fusion physics studies are done in collaboration with major EU fusion laboratories, Hungarian researchers also play an active role in JET diagnostics upgrade and ITER design. Major topics are pellet ablation studies, plasma turbulence diagnosis using Beam Emission Spectroscopy and other techniques, tomography and plasma diagnostics using various neutral beams. In fusion relevant technology R and D Hungary has less records. Before joining EURATOM some materials irradiation studies were done at the Budapest Research Reactor at KFKI-AEKI. The present day fusion technology programme focuses still on irradiation studies, nuclear material database and electromagnetic testing techniques. Increasing the fusion technology research activities is a difficult task, as the competition in Hungarian industry is very strong and the interest of organizations in long-term investments into R and D is rather weak and

  9. Colliding Beam Fusion Reactors

    Science.gov (United States)

    Rostoker, Norman; Qerushi, Artan; Binderbauer, Michl

    2003-06-01

    The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the Fokker-Planck equation. The reactors involve non-Maxwellian plasmas. The calculations are generic in that they do not relate to specific confinement devices. In all cases except for a Tokamak with D-T fuel the recirculating power was found to exceed the fusion power by a large factor. In this paper we criticize the generality claimed for this calculation. The ratio of circulating power to fusion power is calculated for the Colliding Beam Reactor with fuels D-T, D-He3 and p-B11. The results are respectively, 0.070, 0.141 and 0.493.

  10. Materials research for fusion

    Science.gov (United States)

    Knaster, J.; Moeslang, A.; Muroga, T.

    2016-05-01

    Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission reactors. The technological challenges of fusion energy are intimately linked with the availability of suitable materials capable of reliably withstanding the extremely severe operational conditions of fusion reactors. Although fission and fusion materials exhibit common features, fusion materials research is broader. The harder mono-energetic spectrum associated with the deuterium-tritium fusion neutrons (14.1 MeV compared to fusion-relevant neutron source for materials testing is an essential pending step in fusion roadmaps. Structural materials development, together with research on functional materials capable of sustaining unprecedented power densities during plasma operation in a fusion reactor, have been the subject of decades of worldwide research efforts underpinning the present maturity of the fusion materials research programme.

  11. Particle beam fusion progress report, January-June 1980

    International Nuclear Information System (INIS)

    An overview and technical summaries are given for research progress in each of the following general areas: (1) fusion target studies; (2) target experiments; (3) particle beam source theory; (4) diagnostics development; (5) particle beam experiments; (6) pulsed power research and development; (7) pulse power application; and (8) Electron Beam Fusion Accelerator project

  12. Economics of fusion research

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1977-10-15

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

  13. Economics of fusion research

    International Nuclear Information System (INIS)

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

  14. Neutral beams for magnetic fusion

    International Nuclear Information System (INIS)

    Significant advances in forming energetic beams of neutral hydrogen and deuterium atoms have led to a breakthrough in magnetic fusion: neutral beams are now heating plasmas to thermonuclear temperatures, here at LLL and at other laboratories. For example, in our 2XIIB experiment we have injected a 500-A-equivalent current of neutral deuterium atoms at an average energy of 18 keV, producing a dense plasma (1014 particles/cm3) at thermonuclear energy (14 keV or 160 million kelvins). Currently, LLL and LBL are developing beam energies in the 80- to 120-keV range for our upcoming MFTF experiment, for the TFTR tokamak experiment at Princeton, and for the Doublet III tokamak experiment at General Atomic. These results increase our long-range prospects of producing high-intensity beams of energies in the hundreds or even thousands of kilo-electron-volts, providing us with optimistic extrapolations for realizing power-producing fusion reactors

  15. Intense pulsed ion beams for fusion applications

    International Nuclear Information System (INIS)

    The subject of this review paper is the field of intense pulsed ion beam generation and the potential application of the beams to fusion research. Considerable progress has been made over the past six years. The ion injectors discussed utilize the introduction of electrons into vacuum acceleration gaps in conjunction with high voltage pulsed power technology to achieve high output current. Power levels from injectors exceeding 1000 MW/cm2 have been obtained for pulse lengths on the order of 10-7 sec. The first part of the paper treats the physics and technology of intense ion beams. The second part is devoted to applications of intense ion beams in fusion research. A number of potential uses in magnetic confinement systems have been proposed

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

    International Nuclear Information System (INIS)

    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

  17. Materials research for fusion

    Science.gov (United States)

    Knaster, J.; Moeslang, A.; Muroga, T.

    2016-05-01

    Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission reactors. The technological challenges of fusion energy are intimately linked with the availability of suitable materials capable of reliably withstanding the extremely severe operational conditions of fusion reactors. Although fission and fusion materials exhibit common features, fusion materials research is broader. The harder mono-energetic spectrum associated with the deuterium-tritium fusion neutrons (14.1 MeV compared to average for fission neutrons) releases significant amounts of hydrogen and helium as transmutation products that might lead to a (at present undetermined) degradation of structural materials after a few years of operation. Overcoming the historical lack of a fusion-relevant neutron source for materials testing is an essential pending step in fusion roadmaps. Structural materials development, together with research on functional materials capable of sustaining unprecedented power densities during plasma operation in a fusion reactor, have been the subject of decades of worldwide research efforts underpinning the present maturity of the fusion materials research programme.

  18. Frontiers in fusion research

    CERN Document Server

    Kikuchi, Mitsuru

    2011-01-01

    Frontiers in Fusion Research provides a systematic overview of the latest physical principles of fusion and plasma confinement. It is primarily devoted to the principle of magnetic plasma confinement, that has been systematized through 50 years of fusion research. Frontiers in Fusion Research begins with an introduction to the study of plasma, discussing the astronomical birth of hydrogen energy and the beginnings of human attempts to harness the Sun's energy for use on Earth. It moves on to chapters that cover a variety of topics such as: * charged particle motion, * plasma kinetic theory, *

  19. Fusion research principles

    CERN Document Server

    Dolan, Thomas James

    2013-01-01

    Fusion Research, Volume I: Principles provides a general description of the methods and problems of fusion research. The book contains three main parts: Principles, Experiments, and Technology. The Principles part describes the conditions necessary for a fusion reaction, as well as the fundamentals of plasma confinement, heating, and diagnostics. The Experiments part details about forty plasma confinement schemes and experiments. The last part explores various engineering problems associated with reactor design, vacuum and magnet systems, materials, plasma purity, fueling, blankets, neutronics

  20. Cluster-impact fusion, or beam-contaminant fusion? (abstract)

    International Nuclear Information System (INIS)

    Beuhler, Friedlander, and Friedman (BFF) reported anomalously huge D-D fusion rates while bombarding deuterated targets with (D2O)N+ clusters (N∼25--1000) accelerated to ∼325 keV [R. J. Beuhler et al., Phys. Rev. Lett. 63, 1292 (1989); R. J. Beuhler et al., J. Phys. Chem. 94, 7665 (1990)] [i.e., ∼0.3 keV lab energy for D in (D2O)100+]. However, from our analysis of BFF's fusion product spectra, we conclude that their D lab energy was ∼50 keV. Therefore, no gross anomalies exist. Also, from our analysis of the BFF beam-ranging experiments through 500 μg/cm2 of Au, we conclude that light-ion-beam contaminants (e.g., D+ of order 100 keV) have not been ruled out, and are the probable cause of their fusion reactions. This work was supported by LLNL Subcontract B116798, Department of Energy (DOE) Grant No. DE-FG02-91ER54109, DOE Magnetic Fusion Energy Technology Fellowship Program (D. H. Lo), and DOE Fusion Energy Postdoctoral Research Program (Kevin W. Wenzel)

  1. Heavy-Ion Fusion Accelerator Research, 1991

    International Nuclear Information System (INIS)

    This report discusses the following topics: research with multiple- beam experiment MBE-4; induction linac systems experiments; and long- range research and development of heavy-ion fusion accelerators

  2. Important atomic physics issues for ion beam fusion

    International Nuclear Information System (INIS)

    This paper suggests several current atomic physics questions important to ion beam fusion. Among the topics discussed are beam transport, beam-target interaction, and reactor design. The major part of the report is discussion concerning areas of research necessary to better understand beam-target interactions

  3. Intense ion beam research for inertial confinement fusion. Final technical report, 1 October 1981-31 October 1985

    International Nuclear Information System (INIS)

    Theoretical and experimental research has been performed on the application of intense light ion beams to inertial confinement fusion. The following achievements are documented. A 1 TW accelerator (a module of the PBFA 1 device at Sandia National Laboratories, Albuquerque), has been installed at Cornell and it has been used to develop high power magnetically insulated ion diodes. Ion beams at 0.3 TW level have been produced. The use of spectroscopic techniques to diagnose conditions in detail with in magnetically insulated diodes was proposed, and preliminary experiments have been successfully performed. These have revealed the anode plasma density, transverse velocities of ions within the diode (from Doppler broadening of ion emission lines) and the electric field profile in the accelerating gap (from the Stark shifted line profile of especially selected emission lines). Theoretical studies on the effects of lack of symmetry in the electron drift direction on the leakage electron current in a magnetically insulated diode show that even very small perturbations can cause a substantial enhancement of the leakage current. Experiments involving electron flow in a magnetically insulated diode have shown cathode sheath losses to occur in local burst as well as in a smooth manner

  4. Generation of intense ion beams and their application to controlled fusion research

    International Nuclear Information System (INIS)

    Successful generation of pulsed multi-kA proton beams in the energy range 0.2 to 1.7 MeV using existing pulsed power technology has been achieved by three different techniques: reflex triodes, pinched electron-beam diodes and magnetically insulated diodes. Peak current densities in excess of 10 kAcm-2 have been observed on the NRL Gamble II machine and over 1.0 kAcm-2 on the Cornell Neptune machine. Peak total ion currents above 200 kA are produced by Gamble II. The potential applications of intense ion beams to magnetic confinement include (i) plasma heating and (ii) ion rings. A summary of continuous theoretical and experimental investigations on these applications is presented. (author)

  5. Tritium production potential of beam research and magnetic fusion program technologies

    International Nuclear Information System (INIS)

    Regular replenishment of tritium in the nuclear weapons stockpile is essential to maintain our nuclear deterrent. Nuclear reactor facilities presently used for the production of tritium are aging, and their operation is being curtailed awaiting the repairs and upgrades needed to meet modern standards of safety and environment. To provide improved capability in the future, DOE plans to construct a new production reactor. Alternatives to nuclear reactor methods for the production of tritium, mainly electrically-driven accelerator or fusion systems, have been proposed many times in the past. Given the critical national security implications of maintaining adequate tritium production facilities, it is clearly worthwhile for political decision-makers to have a clear and accurate picture of the technical options that could be made available at various points in the future. The goal of this white paper is to summarize available technical information on a set of non-nuclear-reactor options for tritium production with a minimum of advocacy for any one system of implicit assumptions about politically desirable attributes. Indeed, these various options differ considerably in aspects such as the maturity of the technology, the development cost and timescales required, and the capital and operating costs of a typical ''optimized'' facility

  6. Research on modeling of heat source for electron beam welding fusion-solidification zone

    Institute of Scientific and Technical Information of China (English)

    Wang Yajun; Fu Pengfei; Guan Yongjun; Lu Zhijun; Wei Yintao

    2013-01-01

    In this paper,the common heat source model of point and linear heat source in the numerical simulation of electron beam welding (EBW) were summarized and introduced.The combined point-linear heat source model was brought forward and to simulate the welding temperature fields of EBW and predicting the weld shape.The model parameters were put forward and regulated in the combined model,which included the ratio of point heat source to linear heat source Qpr and the distribution of linear heat source Lr.Based on the combined model,the welding temperature fields of EBW were investigated.The results show that the predicted weld shapes are conformable to those of the actual,the temperature fields are reasonable and correct by simulating with combined point-linear heat source model and the typical weld shapes are gained.

  7. Fusion research at ORNL

    International Nuclear Information System (INIS)

    The ORNL Fusion Program includes the experimental and theoretical study of two different classes of magnetic confinement schemes - systems with helical magnetic fields, such as the tokamak and stellarator, and the ELMO Bumpy Torus (EBT) class of toroidally linked mirror systems; the development of technologies, including superconducting magnets, neutral atomic beam and radio frequency (rf) heating systems, fueling systems, materials, and diagnostics; the development of databases for atomic physics and radiation effects; the assessment of the environmental impact of magnetic fusion; and the design of advanced demonstration fusion devices. The program involves wide collaboration, both within ORNL and with other institutions. The elements of this program are shown. This document illustrates the program's scope; and aims by reviewing recent progress

  8. Accelerator and fusion research division. 1992 Summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations.

  9. Conference on Norwegian fusion research

    International Nuclear Information System (INIS)

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

  10. Fusion research in India

    International Nuclear Information System (INIS)

    The economic growth of our country demands a rapid increase in the energy output. Fusion is one such alternate clean source of energy to contribute in the energy mix towards the second half of the century, with a virtually inexhaustible fuel supply. The environmental impact of fusion would be acceptable and relatively safe. These advantages have driven the world fusion research programme since its inception. Till a pure fusion energy source is available, it is worthwhile to develop it for the benefit of conventional fission fuel preparation and other various usages. Indian National Fusion Programme was initiated by indigenously developing the first Indian Tokamak, ADITYA, successfully commissioned in 1989 and has been generating interesting scientific results on various topics. The next major program at Institute for Plasma Research (IPR) has been to construct a Steady State Superconducting Tokamak (SST-1) by mix of import and indigenous development. After successful engineering validation of the subsystems in integrated operations, successful machine operation has been continued. Since then, the machine has been upgraded with a graphite first wall. As a strategy towards leapfrogging to save time, IPR and Department of Atomic Energy (DAE) decided on India’s participation in the International Thermonuclear Experimental Reactor (ITER) as a full partner, unique features of which will be its ability to operate for long durations and at power levels ∼500 MW sufficient to demonstrate the physics of burning plasma in a power plant like environment. It will also serve as a test-bed for additional fusion power plant technologies. To accelerate the domestic fusion research programme with integration of knowledge gained from ITER, we would embark upon design of a smaller fusion machine which will use already available technologies to produce controlled fusion reactions and use it as an energetic neutron source for test of materials developed for future fusion reactors

  11. Contribution of Beam-Driven Fusion in Pure Deuterium Plasma

    International Nuclear Information System (INIS)

    The urgent and ultimate goal of the fusion research is to accomplish a fusion reactor functioning practically. Though the first fusion reactor is expected to use a DT fuel, most fusion researchers have studied H or D plasmas instead of DT plasma because of radioactivity and resource problems. DD plasma experiments, now a usual trend, can give useful information on the fusion plasma physics, tritium retention, alpha particle transport, neutronics, and so on at a safe controlled radiation level. The KSTAR tokamak, all-superconductor world level fusion research device, has been operated with pure deuterium plasmas since the 2010 campaign, however, the thermal fusion reaction rate is still far below significant because of low plasma temperature. The NBI system equipped on the KSTAR tokamak can deliver more than 1.5 MW input power of deuterium neutral beam at 100 keV with one ion source, which have contributed to making H-mode plasmas for several seconds. The next goal of the NBI input power at the 2012 campaign is 3.5 MW with two ion sources. Hot ions generated from the deuterium neutral beam injected into the D plasma can produce beam-driven fusion reactions at a much more notable level than thermal ones. Contribution of deuterium neutral beam injection on the fusion reactions in a D plasma is preliminarily assessed here

  12. Experimental results of a sheet-beam, high power, FEL amplifier with application to magnetic fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, S.; Destler, W.W.; Granatstein, V.L. [Univ. of Maryland, College Park, MD (United States)] [and others

    1995-12-31

    The experimental study of sheet-beam FELs as candidate millimeter-wave sources for heating magnetic fusion plasmas has achieved a major milestone. In a proof-of-principle, pulsed experiment, saturated FEL amplifier operation was achieved with 250 kW of output power at 86 GHz. Input microwave power was 1 kW, beam voltage was 450 kV and beam current was 17 A. The planar wiggler had a peak value of 3.8 kG, a period of 0.96 cm and was 71 cm long. The linear gain of 30 dB, saturated gain of 24 dB and saturated efficiency of 3% all are in good agreement with theoretical prediction. Follow-on work would include development of a thermionic sheet-beam electron-gun compatible with CW FEL operation, adding a section of tapered wiggler to increase the output power to levels in excess of 1 megawatt, and increasing the FEL frequency.

  13. Fusion research in Japan

    International Nuclear Information System (INIS)

    The importance of fusion power to Japan is perhaps the greatest among nations of the world. The scarcity of other energy resources such as oil, coal, and even solar energy (as the land is small) makes it almost imperative to depend on nuclear power for her primary energy need in the future. A high population density means that the radiation hazard problems are very much greater than in other nations such as the USA. Earthquakes and unstable geological features pose a rather difficult problem in storing radioactive wastes which tend to be produced more from ordinary fission reactors, including breeders, rather than from fusion reactors, if the latter are practicable. Japan has two research groups actively engaged in fusion research, one is under the direction of Japan Atomic Energy Commission, and the other is under the direction of Ministry of Education. Work covers both reactor core plasmas and reactor technology. Japan is presently making a five-year plan to do scientific feasibility experiments in the scale comparable to the so-called D-T burner (USA) or JET

  14. Inertial-confinement fusion driven by heavy-ion beams

    International Nuclear Information System (INIS)

    Fundamental concepts, current status and future prospects of heavy-ion-driven inertial-confinement fusion are described. Target physics issues are emphasized. An account is given of experimental programs now under way, including beam/plasma interaction and accelerator physics experiments. Plans for high-intensity-beam/target research using heavy-ion beams from the synchrotron at GSI (Darmstadt, FRG) are presented. (orig.)

  15. Inertial confinement fusion driven by heavy-ion beams

    International Nuclear Information System (INIS)

    Fundamental concepts, current status and future prospects of heavy-ion-driven inertial confinement fusion are described. Target physics issues are emphasised. An account is given of experimental programmes now under way, including beam/plasma interaction and accelerator physics experiments. Plans for high-intensity beam/target research using heavy-ion beams from the synchrotron at GSI, Darmstadt, FRG are presented. (author)

  16. Heavy-ion fusion accelerator research, 1989

    International Nuclear Information System (INIS)

    This report discusses the following topics on heavy-ion fusion accelerator research: MBE-4: the induction-linac approach; transverse beam dynamics and current amplification; scaling up the results; through ILSE to a driver; ion-source and injector development; and accelerator component research and development

  17. A brief overview of Tokamak fusion research

    International Nuclear Information System (INIS)

    Fusion, the nuclear engine that powers the sun and stars, has been pursued by scientists for decades as the ultimate source of energy. It promises an almost inexhaustible fuel supply with the oceans containing sufficient fusion fuel to outlast the expected life of the sun. Fusion is a process whose waste is inert and whose components know no geographical bounds. Scientists have pondered the laws governing the fusion process since the 1940's, and since the late 1950's laboratory devices have been constructed to test and further develop the theories. To achieve fusion, the joining of light atomic nuclei (as opposed to the splitting of heavy elements in the fission process), the natural tendency of the nuclei to repel each other due to their like electrical charges must be overcome. As the fusion takes place, some of the matter of the nuclei is converted to energy. In the stars fusion is accomplished largely by enormous gravitational forces. On earth the fusion fuel must be heated by other means to increase the energy of the particles to force them to fuse. Therein lies the challenge of fusion research - how to heat sufficient matter to hundreds of millions of degrees and contain it long enough for a controlled and sustained fusion reaction to take place. The method that presently shows the most promise is to contain a plasma (an ionized gas - the fourth state of matter) in a magnetic field while heating the plasma by means of high energy neutral particle beams or radio frequency waves

  18. Cold fusion research

    International Nuclear Information System (INIS)

    I am pleased to forward to you the Final Report of the Cold Fusion Panel. This report reviews the current status of cold fusion and includes major chapters on Calorimetry and Excess Heat, Fusion Products and Materials Characterization. In addition, the report makes a number of conclusions and recommendations, as requested by the Secretary of Energy

  19. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  20. Fusion using radioactive ion beams

    Indian Academy of Sciences (India)

    A M Vinodkumar

    2010-07-01

    The capture-fission cross-section is measured for the collision of the massive nucleus 132Sn with 96Zr at near-barrier energies and compared with the collision of 124Sn with 96Zr. This study gives insight into fusion enhancement and hindrance in systems involving neutron-rich nuclei. The dinuclear system model (DNS) calculations describe the excitation function reasonably well and if we use the barrier heights predicted by this model we can conclude that fusion hindrance (represented by extra push energy) is greater for the more neutron-rich systems. The fusion excitation function for 9Li+70Zn and 9Li+208Pb systems are measured for near-barrier energies using ISAC1 and ISAC2 Facilities at TRIUMF. The -emitting evaporation residues (211−214At) are stopped in the 208Pb target and their decay is measured. The measured excitation function shows evidence for large enhancements in the sub-barrier energies, which is not accounted by current theoretical models. Suppression of the above-barrier cross-section with respect to these theoretical models are also seen.

  1. Overview of US heavy ion fusion research

    International Nuclear Information System (INIS)

    Significant experimental and theoretical progress has been made in the U.S. heavy ion fusion program on high-current sources, injectors, transport, final focusing, chambers and targets for high energy density physics (HEDP) and inertial fusion energy (IFE) driven by induction linac accelerators. One focus of present research is the beam physics associated with quadrupole focusing of intense, space-charge dominated heavy-ion beams, including gas and electron cloud effects at high currents, and the study of long-distance-propagation effects such as emittance growth due to field errors in scaled experiments. A second area of emphasis in present research is the introduction of background plasma to neutralize the space charge of intense heavy ion beams and assist in focusing the beams to a small spot size. In the near future, research will continue in the above areas, and a new area of emphasis will be to explore the physics of neutralized beam compression and focusing to high intensities required to heat targets to high energy density conditions as well as for inertial fusion energy. (author)

  2. Overview of US heavy ion fusion research

    International Nuclear Information System (INIS)

    Significant experimental and theoretical progress has been made in the U.S. heavy ion fusion program on high-current sources, injectors, transport, final focusing, chambers and targets for high energy density physics (HEDP) and inertial fusion energy (IFE) driven by induction linac accelerators. One focus of present research is the beam physics associated with quadrupole focusing of intense, space-charge dominated heavy-ion beams, including gas and electron cloud effects at high currents, and the study of long-distance-propagation effects such as emittance growth due to field errors in scaled experiments. A second area of emphasis in present research is the introduction of background plasma to neutralize the space charge of intense heavy ion beams and assist in focusing the beams to a small spot size. In the near future, research will continue in the above areas, and a new area of emphasis will be to explore the physics of neutralized beam compression and focusing to high intensities required to heat targets to high energy density conditions as well as for inertial fusion energy

  3. INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS

    Energy Technology Data Exchange (ETDEWEB)

    Sharp, W. M.; Friedman, A.; Grote, D. P.; Barnard, J. J.; Cohen, R. H.; Dorf, M. A.; Lund, S. M.; Perkins, L. J.; Terry, M. R.; Logan, B. G.; Bieniosek, F. M.; Faltens, A.; Henestroza, E.; Jung, J. Y.; Kwan, J. W.; Lee, E. P.; Lidia, S. M.; Ni, P. A.; Reginato, L. L.; Roy, P. K.; Seidl, P. A.; Takakuwa, J. H.; Vay, J.-L.; Waldron, W. L.; Davidson, R. C.; Gilson, E. P.; Kaganovich, I. D.; Qin, H.; Startsev, E.; Haber, I.; Kishek, R. A.; Koniges, A. E.

    2011-03-31

    Intense heavy-ion beams have long been considered a promising driver option for inertial-fusion energy production. This paper briefly compares inertial confinement fusion (ICF) to the more-familiar magnetic-confinement approach and presents some advantages of using beams of heavy ions to drive ICF instead of lasers. Key design choices in heavy-ion fusion (HIF) facilities are discussed, particularly the type of accelerator. We then review experiments carried out at Lawrence Berkeley National Laboratory (LBNL) over the past thirty years to understand various aspects of HIF driver physics. A brief review follows of present HIF research in the US and abroad, focusing on a new facility, NDCX-II, being built at LBNL to study the physics of warm dense matter heated by ions, as well as aspects of HIF target physics. Future research directions are briefly summarized.

  4. Inertial Fusion Driven By Intense Heavy-Ion Beams

    International Nuclear Information System (INIS)

    Intense heavy-ion beams have long been considered a promising driver option for inertial-fusion energy production. This paper briefly compares inertial confinement fusion (ICF) to the more-familiar magnetic-confinement approach and presents some advantages of using beams of heavy ions to drive ICF instead of lasers. Key design choices in heavy-ion fusion (HIF) facilities are discussed, particularly the type of accelerator. We then review experiments carried out at Lawrence Berkeley National Laboratory (LBNL) over the past thirty years to understand various aspects of HIF driver physics. A brief review follows of present HIF research in the US and abroad, focusing on a new facility, NDCX-II, being built at LBNL to study the physics of warm dense matter heated by ions, as well as aspects of HIF target physics. Future research directions are briefly summarized.

  5. Longitudinal beam dynamics for heavy ion fusion

    International Nuclear Information System (INIS)

    The longitudinal wall impedance instability is of great interest for a heavy ion fusion (HIF) driver because complete stabilization of this mode via momentum spread is impractical due to requirements of focusing the beam onto the inertial confinement fusion target. This instability is being studied with the WARPrz particle-in-cell code. The impedance of the induction linac modules is modeled as a wall impedance corresponding to a continuum of resistors and capacitors in parallel. We discuss simulations of the this instability, including reflections of perturbations off the beam end and the effects of finite temperature, and simulations of errors in intermittently-applied axial confining fields as a seed for this instability. We also present very long simulations in which we look for beam equilibria

  6. Fusion research at Culham site

    International Nuclear Information System (INIS)

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

  7. Whither fusion research?

    International Nuclear Information System (INIS)

    The author maintains that the magnetic fusion program is ready for a dramatic change of course. The author's criteria for a desirable fusion power reactor are: it must produce power at a competitive price; it must work with high reliability and maintenance must be easy, fast and low cost, and that the fusion reactor must be safe and not damage the environment. The author's feelings are based on years of observation of the utility industry in general and commercial nuclear power development in particular. The author's views on the undesirability of tokamaks are discussed. Two concepts discussed as alternatives are the Reversed Field Pinch (RFP) and the spheromak

  8. Induction linacs for heavy ion fusion research

    International Nuclear Information System (INIS)

    The new features of employing an induction linac as a driver for inertial fusion involve (1) transport of high-current low-emittance heavy ion beams, (2) multiple independently-focussed beams threading the same accelerator structure, and (3) synthesis of voltage waveforms to accomplish beam current amplification. A research program is underway at LBL to develop accelerators that test all these features with the final goal of producing an ion beam capable of heating matter to approx. 70 eV. This paper presents a discussion of some properties of induction linacs and how they may be used for HIF research. Physics designs of the High Temperature Experiment (HTE) and the Multiple Beam Experiment (MBE) accelerators are presented along with initial concepts of the MBE induction units

  9. Induction linacs for heavy ion fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Fessenden, T.J.

    1984-05-01

    The new features of employing an induction linac as a driver for inertial fusion involve (1) transport of high-current low-emittance heavy ion beams, (2) multiple independently-focussed beams threading the same accelerator structure, and (3) synthesis of voltage waveforms to accomplish beam current amplification. A research program is underway at LBL to develop accelerators that test all these features with the final goal of producing an ion beam capable of heating matter to approx. 70 eV. This paper presents a discussion of some properties of induction linacs and how they may be used for HIF research. Physics designs of the High Temperature Experiment (HTE) and the Multiple Beam Experiment (MBE) accelerators are presented along with initial concepts of the MBE induction units.

  10. Is fusion research worth it?

    International Nuclear Information System (INIS)

    Long-term energy R and D such as fusion needs to be valued as a 'real option'. The R and D itself does not provide energy, but rather the option to construct and operate energy-producing systems. An initial analysis of this problem [Goldenberg, Linton, Nuclear Fusion R and D, Energy Risk, 2006] used an inversion of the Black-Scholes formula to take explicit account of fluctuations in the real value of energy. That study concluded that for reasonable assumptions about the operating cost of fusion power plants, the fusion option was cost effective. Here we use a simpler estimate of the future value of energy, but look more carefully at the question of the opportunity cost of engaging in fusion R and D. We find again that fusion research is a good investment. (author)

  11. Fusion research programme in India

    Indian Academy of Sciences (India)

    Shishir Deshpande; Predhiman Kaw

    2013-10-01

    The fusion energy research program of India is summarized in the context of energy needs and scenario of tokamak advancements on domestic and international fronts. In particular, the various technologies that will lead us to ultimately build a fusion power reactor are identified along with the steps being taken for their indigenous development.

  12. Alpha particles in fusion research

    International Nuclear Information System (INIS)

    This collection of 39 (mostly view graph) presentations addresses various aspects of alpha particle physics in thermonuclear fusion research, including energy balance and alpha particle losses, transport, the influence of alpha particles on plasma stability, helium ash, the transition to and sustainment of a burning fusion plasma, as well as alpha particle diagnostics. Refs, figs and tabs

  13. Accelerator and Fusion Research Division: summary of activities, 1983

    International Nuclear Information System (INIS)

    The activities described in this summary of the Accelerator and Fusion Research Division are diverse, yet united by a common theme: it is our purpose to explore technologically advanced techniques for the production, acceleration, or transport of high-energy beams. These beams may be the heavy ions of interest in nuclear science, medical research, and heavy-ion inertial-confinement fusion; they may be beams of deuterium and hydrogen atoms, used to heat and confine plasmas in magnetic fusion experiments; they may be ultrahigh-energy protons for the next high-energy hadron collider; or they may be high-brilliance, highly coherent, picosecond pulses of synchrotron radiation

  14. Conceptual design of light ion beam inertia nuclear fusion reactors

    International Nuclear Information System (INIS)

    Light ion beam, inertia nuclear fusion system drew attention recently as one of the nuclear fusion systems for power reactors in the history of the research on nuclear fusion. Its beginning seemed to be the judgement that the implosion of fusion fuel pellets with light ions can be realized with the light ions which can be obtained in view of accelerator techniques. Of course, in order to generate practically usable nuclear fusion reaction by this system and maintain it, many technical difficulties must be overcome. This research was carried out for the purpose of discovering such technical problems and searching for their solution. At the time of doing the works, the following policy was adopted. Though their is the difference of fine and rough, the design of a whole reactor system is performed conformably. In order to make comparison with other reactor types and nuclear fusion systems, the design is carried out as the power plant of about one million kWe output. As the extent of the design, the works at conceptual design stage are performed to present the concept of design which satisfies the required function. Basically, the design is made from conservative standpoint. This research of design was started in 1981, and in fiscal 1982, the mutual adjustment among the design of respective parts was performed on the basis of the results in 1981, and the possible revision and new proposal were investigated. (Kako, I.)

  15. [Fusion energy research

    International Nuclear Information System (INIS)

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

  16. (Fusion energy research)

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, C.A. (ed.)

    1988-01-01

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

  17. Nuclear fusion research in Australia

    International Nuclear Information System (INIS)

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

  18. Collaborations in fusion research

    International Nuclear Information System (INIS)

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

  19. Fusion reactor development using high power particle beams

    International Nuclear Information System (INIS)

    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.)

  20. Relativistic-electron-beam-induced fusion

    International Nuclear Information System (INIS)

    The interaction of a focussed relativistic electron beam (REB) with a solid target has been investigated. The beam performance of the REB generator ''REIDEN III'' is 500 kV, 80 kA at a focal spot of 1.5 mm diameter, which gives 2X1012Wcm-2. High-temperature dense plasmas are produced at the focal point on the solid target. It expands radially along the target surface. The measured electron temperature (1-2 keV) and the ion energy (approximately 2 keV) endorse the existence of enhanced REB absorption in a dense plasma. The neutrons observed (approximately 109/shot, 2.45 MeV) in the case of a CD2 target are of thermonuclear origin and compatible with the plasma temperature. On the assumption that the electron beam of radius r is stopped at a length Λ and deposits its energy, the energy balance equation is approximately given by πr2Λn1kT=IVtau. On inserting beam current I, voltage V, pulse time tau and density n1, the energy deposition distance Λ can be estimated. For a fusion temperature of 1 keV, the distance Λ must be two orders of magnitude shorter than the simple classical stopping length, which seems to be due to non-linear coupling. A pellet implosion experiment of a multi-structure target has been performed. (author)

  1. Maryland controlled fusion research program. Volume I

    International Nuclear Information System (INIS)

    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

  2. Focus on nuclear fusion research

    Czech Academy of Sciences Publication Activity Database

    Křenek, Petr; Mlynář, Jan

    2011-01-01

    Roč. 61, - (2011), s. 62-63. ISSN 0375-8842 Institutional research plan: CEZ:AV0Z20430508 Keywords : ITER * COMPASS * fusion energy * tokamak * EURATOM Subject RIV: BL - Plasma and Gas Discharge Physics http://www.ipp.cas.cz/Tokamak/clanky/energetika_COMPASS.pdf

  3. Colliding beam fusion reactor space propulsion system

    Science.gov (United States)

    Wessel, Frank J.; Binderbauer, Michl W.; Rostoker, Norman; Rahman, Hafiz Ur; O'Toole, Joseph

    2000-01-01

    We describe a space propulsion system based on the Colliding Beam Fusion Reactor (CBFR). The CBFR is a high-beta, field-reversed, magnetic configuration with ion energies in the range of hundreds of keV. Repetitively-pulsed ion beams sustain the plasma distribution and provide current drive. The confinement physics is based on the Vlasov-Maxwell equation, including a Fokker Planck collision operator and all sources and sinks for energy and particle flow. The mean azimuthal velocities and temperatures of the fuel ion species are equal and the plasma current is unneutralized by the electrons. The resulting distribution functions are thermal in a moving frame of reference. The ion gyro-orbit radius is comparable to the dimensions of the confinement system, hence classical transport of the particles and energy is expected and the device is scaleable. We have analyzed the design over a range of 106-109 Watts of output power (0.15-150 Newtons thrust) with a specific impulse of, Isp~106 sec. A 50 MW propulsion system might involve the following parameters: 4-meters diameter×10-meters length, magnetic field ~7 Tesla, ion beam current ~10 A, and fuels of either D-He3,P-B11,P-Li6,D-Li6, etc. .

  4. Reduction in TFTR [Tokamak Fusion Test Reactor] fusion reaction rate by unbalanced beam injection and rotation

    International Nuclear Information System (INIS)

    In TFTR plasmas at low to moderate density, the highest fusion energy gain Q/sub dd/ (D-D fusion power/injected power P/sub b/) is obtained with nearly balanced co- and counter-injection of neutral beams. For a given beam power, significantly unbalanced injection reduces Q/sub dd/ because the accompanying plasma rotation reduces the beam-target fusion reactivity, the fast-ion slowing-down time, and the beam-beam reaction rate, while and decrease from their maximum values. 9 refs., 3 figs., 1 tab

  5. Fuel Target Implosion in Ion beam Inertial Confinement Fusion

    CERN Document Server

    Kawata, Shigeo

    2015-01-01

    The numerical results for the fuel target implosion are presented in order to clarify the target physics in ion beam inertial fusion. The numerical analyses are performed for a direct-driven ion beam target. In the paper the following issues are studied: the beam obliquely incidence on the target surface, the plasma effect on the beam-stopping power, the beam particle energy, the beam time duration, the target radius, the beam input energy and the non-uniformity effect on the fuel target performance. In this paper the beam ions are protons.

  6. Inertial fusion research: Annual technical report, 1985

    International Nuclear Information System (INIS)

    This report describes the inertial confinement fusion (ICF) research activities undertaken at KMS Fusion (KMSF) during 1985. It is organized into three main technical sections; the first covers fusion experiments and theoretical physics, the second is devoted to progress in materials development and target fabrication, and the third describes laser technology research. These three individual sections have been cataloged separately

  7. Particle beam fusion progress report for 1989

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States). Pulsed Power Sciences Center

    1994-08-01

    This report summarizes the progress on the pulsed power approach to inertial confinement fusion. In 1989, the authors achieved a proton focal intensity of 5 TW/cm{sup 2} on PBFA-II in a 15-cm-radius applied magnetic-field (applied-B) ion diode. This is an improvement by a factor of 4 compared to previous PBFA-II experiments. They completed development of the three-dimensional (3-D), electromagnetic, particle-in-cell code QUICKSILVER and obtained the first 3-D simulations of an applied-B ion diode. The simulations, together with analytic theory, suggest that control of electromagnetic instabilities could reduce ion divergence. In experiments using a lithium fluoride source, they delivered 26 kJ of lithium energy to the diode axis. Rutherford-scattered ion diagnostics have been developed and tested using a conical foil located inside the diode. They can now obtain energy density profiles by using range filters and recording ion images on nuclear track recording film. Timing uncertainties in power flow experiments on PBFA-II have been reduced by a factor of 5. They are investigating three plasma opening switches that use magnetic fields to control and confine the injected plasma. These new switches provide better power flow than the standard plasma erosion switch. Advanced pulsed-power fusion drivers will require extraction-geometry applied-B ion diodes. During this reporting period, progress was made in evaluating the generation, transport, and focus of multiple ion beams in an extraction geometry and in assessing the probable damage to a target chamber first wall.

  8. Particle beam fusion progress report for 1989

    International Nuclear Information System (INIS)

    This report summarizes the progress on the pulsed power approach to inertial confinement fusion. In 1989, the authors achieved a proton focal intensity of 5 TW/cm2 on PBFA-II in a 15-cm-radius applied magnetic-field (applied-B) ion diode. This is an improvement by a factor of 4 compared to previous PBFA-II experiments. They completed development of the three-dimensional (3-D), electromagnetic, particle-in-cell code QUICKSILVER and obtained the first 3-D simulations of an applied-B ion diode. The simulations, together with analytic theory, suggest that control of electromagnetic instabilities could reduce ion divergence. In experiments using a lithium fluoride source, they delivered 26 kJ of lithium energy to the diode axis. Rutherford-scattered ion diagnostics have been developed and tested using a conical foil located inside the diode. They can now obtain energy density profiles by using range filters and recording ion images on nuclear track recording film. Timing uncertainties in power flow experiments on PBFA-II have been reduced by a factor of 5. They are investigating three plasma opening switches that use magnetic fields to control and confine the injected plasma. These new switches provide better power flow than the standard plasma erosion switch. Advanced pulsed-power fusion drivers will require extraction-geometry applied-B ion diodes. During this reporting period, progress was made in evaluating the generation, transport, and focus of multiple ion beams in an extraction geometry and in assessing the probable damage to a target chamber first wall

  9. Accelerator and Fusion Research Division annual report, fiscal year 1980, October 1979-September 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-01

    Research during October 1979 to September 1980 is summarized. Areas covered include: accelerator operations; positron-electron project; stochastic beam cooling; high-field superconducting magnets; accelerator theory; neutral beam sources; and heavy ion fusion. (GHT)

  10. Accelerator and Fusion Research Division annual report, fiscal year 1980, October 1979-September 1980

    International Nuclear Information System (INIS)

    Research during October 1979 to September 1980 is summarized. Areas covered include: accelerator operations; positron-electron project; stochastic beam cooling; high-field superconducting magnets; accelerator theory; neutral beam sources; and heavy ion fusion

  11. Polarization beam smoothing for inertial confinement fusion

    International Nuclear Information System (INIS)

    For both direct and indirect drive approaches to inertial confinement fusion (ICF) it is imperative to obtain the best possible drive beam uniformity. The approach chosen for the National Ignition Facility uses a random-phase plate to generate a speckle pattern with a precisely controlled envelope on target. A number of temporal smoothing techniques can then be employed to utilize bandwidth to rapidly change the speckle pattern, and thus average out the small-scale speckle structure. One technique which generally can supplement other smoothing methods is polarization smoothing (PS): the illumination of the target with two distinct and orthogonally polarized speckle patterns. Since these two polarizations do not interfere, the intensity patterns add incoherently, and the rms nonuniformity can be reduced by a factor of (√2). A number of PS schemes are described and compared on the basis of the aggregate rms and the spatial spectrum of the focused illumination distribution. The (√2) rms nonuniformity reduction of PS is present on an instantaneous basis and is, therefore, of particular interest for the suppression of laser plasma instabilities, which have a very rapid response time. When combining PS and temporal methods, such as smoothing by spectral dispersion (SSD), PS can reduce the rms of the temporally smoothed illumination by an additional factor of (√2). However, it has generally been thought that in order to achieve this reduction of (√2), the increased divergence of the beam from PS must exceed the divergence of SSD. It is also shown here that, over the time scales of interest to direct or indirect drive ICF, under some conditions PS can reduce the smoothed illumination rms by nearly (√2) even when the PS divergence is much smaller than that of SSD. (c) 2000 American Institute of Physics

  12. History of Nuclear Fusion Research in Japan

    Science.gov (United States)

    Iguchi, Harukazu; Matsuoka, Keisuke; Kimura, Kazue; Namba, Chusei; Matsuda, Shinzaburo

    In the late 1950s just after the atomic energy research was opened worldwide, there was a lively discussion among scientists on the strategy of nuclear fusion research in Japan. Finally, decision was made that fusion research should be started from the basic, namely, research on plasma physics and from cultivation of human resources at universities under the Ministry of Education, Science and Culture (MOE). However, an endorsement was given that construction of an experimental device for fusion research would be approved sooner or later. Studies on toroidal plasma confinement started at Japan Atomic Energy Research Institute (JAERI) under the Science and Technology Agency (STA) in the mid-1960s. Dualistic fusion research framework in Japan was established. This structure has lasted until now. Fusion research activities over the last 50 years are described by the use of a flowchart, which is convenient to glance the historical development of fusion research in Japan.

  13. Recent fusion research in the National Institute for Fusion Science

    International Nuclear Information System (INIS)

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

  14. SIMULATION OF INTENSE BEAMS FOR HEAVY ION FUSION

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, A

    2004-06-10

    Computer simulations of intense ion beams play a key role in the Heavy Ion Fusion research program. Along with analytic theory, they are used to develop future experiments, guide ongoing experiments, and aid in the analysis and interpretation of experimental results. They also afford access to regimes not yet accessible in the experimental program. The U.S. Heavy Ion Fusion Virtual National Laboratory and its collaborators have developed state-of-the art computational tools, related both to codes used for stationary plasmas and to codes used for traditional accelerator applications, but necessarily differing from each in important respects. These tools model beams in varying levels of detail and at widely varying computational cost. They include moment models (envelope equations and fluid descriptions), particle-in-cell methods (electrostatic and electromagnetic), nonlinear-perturbative descriptions (''{delta}f''), and continuum Vlasov methods. Increasingly, it is becoming clear that it is necessary to simulate not just the beams themselves, but also the environment in which they exist, be it an intentionally-created plasma or an unwanted cloud of electrons and gas. In this paper, examples of the application of simulation tools to intense ion beam physics are presented, including support of present-day experiments, fundamental beam physics studies, and the development of future experiments. Throughout, new computational models are described and their utility explained. These include Mesh Refinement (and its dynamic variant, Adaptive Mesh Refinement); improved electron cloud and gas models, and an electron advance scheme that allows use of larger time steps; and moving-mesh and adaptive-mesh Vlasov methods.

  15. Fuel Target Implosion in Ion beam Inertial Confinement Fusion

    OpenAIRE

    Kawata, Shigeo

    2015-01-01

    The numerical results for the fuel target implosion are presented in order to clarify the target physics in ion beam inertial fusion. The numerical analyses are performed for a direct-driven ion beam target. In the paper the following issues are studied: the beam obliquely incidence on the target surface, the plasma effect on the beam-stopping power, the beam particle energy, the beam time duration, the target radius, the beam input energy and the non-uniformity effect on the fuel target perf...

  16. History and organizations of Japanese fusion research

    International Nuclear Information System (INIS)

    From the Department of Electrical Engineering, University of Tokyo, a historical review of fusion research and development in Japan is given. A table emphasizes the historical evolution of Japanese activities in controlledthermonuclear reac ions. Topics include nuclear fusion R and D organizations and research subjects undertaken, the fusion RandD budget in the past decade, the time evolution of the total fusion RandD annual budget of Japan, steering organizations, of RandD institutions, and the location of fusion research institutions in Japan

  17. Induction linac drivers for commercial heavy-ion beam fusion

    International Nuclear Information System (INIS)

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

  18. A. Sakharov and Fusion Research

    Science.gov (United States)

    Coppi, Bruno

    2012-02-01

    In the landmark paper by Tamm and Sakharov [1], a controlled nuclear fusion reactor based on an axisymmetric magnetic confinement configuration whose principles remain valid to this day, was proposed. In the light of present understanding of plasma physics the virtues (e.g. that of considering the D-D reaction) and the shortcomings of this paper are pointed out. In fact, relatively recent results of theoretical plasma physics (e.g. discovery of the so called second stability region) and advances in high field magnet technology have made it possible to identify the parameters of meaningful experiments capable of exploring D-D and D-^3He burn conditions. At the same time an experimental program (IGNIR) has been undertaken through a (funded) collaboration between Italy and Russia to investigate D-T plasmas close to ignition conditions based on an advanced high field toroidal confinement configuration. A. Sakharov envisioned a bolder approach to fusion research than that advocated by some of his contemporaries. The time taken to design and decide to fabricate the first experiment capable of reaching ignition conditions is due in part to the problem of gaining an adequate understanding the expected physics of fusion burning plasmas. However, most of the relevant financial effort has gone in the pursuit of slow and indirect enterprises complying with the ``playing it safe'' tendencies of large organizations or motivated by the purpose to develop technologies or maintain a high level of expertise in plasma physics to the expected benefit of other kinds of endeavors. The creativity demonstrated by A. Sakharov in dealing with civil rights and disarmament issues is needed, while maintaining our concerns for energy and the environment on a global scale, to orient the funding for fusion research toward a direct and well based scientific effort on concepts for which a variety of developments can be envisioned. These can span from uncovering new physics relevant, for instance

  19. Lasers for inertial confinement fusion research

    International Nuclear Information System (INIS)

    This report contains a discussion of the advances that have taken place in the development of lasers for inertial confinement fusion research since the AECL Laser Fusion Working Party study (AECL-4840) in 1973. It is intended primarily as input to the current Fusion Status Study Group but also as general background information for the Laser Fusion Progress section of the Physics Advanced Systems Study Committee. (auth)

  20. Effects of Collisional Dissipation on the "Colliding Beam Fusion Reactor "

    Science.gov (United States)

    Lampe, Martin; Manheimer, Wallace M.

    1998-11-01

    Rostoker, Binderbauer and Monkhorst have recently proposed a "colliding beam fusion reactor" (CBFR) for use with the p-B11 reaction. We have examined the various dissipative processes resulting from Coulomb collisions, and have concluded that the CBFR equilibrium cannot be sustained for long enough to permit net fusion gain. There are many collisional processes which occur considerably faster than fusion, and result in particle loss, energy loss, or detuning of the resonant energy for the p-B reaction. Pitch-angle scattering of protons off the boron beam, which occurs 100 times faster than fusion, isotropizes the proton beam and results in proton loss. Energy exchange between protons and boron, which is 20 times faster than fusion, detunes the resonance. Proton-proton scattering, which is faster than fusion for all CBFR scenarios, Maxwellianizes the protons and thus detunes the resonance. Ion-electron collisions lead indirectly to a friction between the two ion beams, which is typically fast compared to the fusion process. Results of Fokker-Planck analyses of each process will be shown.

  1. Vortex stabilized electron beam compressed fusion grade plasma

    International Nuclear Information System (INIS)

    Most inertial confinement fusion schemes are comprised of highly compressed dense plasmas. Those schemes involve short, extremely high power, short pulses of beams (lasers, particles) applied to lower density plasmas or solid pellets. An alternative approach could be to shoot an intense electron beam through very dense, atmospheric pressure, vortex stabilized plasma.

  2. West European magnetic confinement fusion research

    International Nuclear Information System (INIS)

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

  3. Nuclear Fusion Fuel Cycle Research Perspectives

    International Nuclear Information System (INIS)

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

  4. Nuclear Fusion Fuel Cycle Research Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin [KAERI, Daejeon (Korea, Republic of); Yun, Sei-Hun [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

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

  5. Inertial confinement fusion research at Osaka. New developments in laser energy drivers, laser and REB fusion research

    International Nuclear Information System (INIS)

    The present approach to inertial confinement fusion is based on understanding the physics of beam-plasma interaction and implosion. The Institute of Laser Engineering, Osaka, is now pursuing project 'Kongoh' which includes the Gekko (glass laser) programme, the Lekko (CO2 laser) programme and the Reiden experiment (REB), a scientific feasibility experiment. Lasers are the most developed energy drivers and are of great value in fundamental fusion research by implosion. REB has a good performance efficiency, and is suitable for a reactor scheme, while beam transport is rather cumbersome owing to plasma instability. Successful implosion experiments by glass microballoon have been performed. Interesting data on laser coupling have been obtained. (author)

  6. Accelerator research for heavy ion inertial fusion

    International Nuclear Information System (INIS)

    It is now one decade since serious consideration was first given to the use of heavy ion accelerators for inertial confinement fusion. After an initial period of wide-ranging studies, the US program settled on an induction linac method proposed by Lawrence Berkeley Laboratory (LBL). The ion kinetic energy is modest (30-100 MeV/amu, 5-10 GeV total) but intense beam currents of order 1 kA per beam in 10-30 beams are required on target in a short pulse of order 10-20 ns. In this review the conceptual designs are described, together with recent theory and experiments on high-current beam transport and use of multiple beams. Parallel efforts in West Germany, Japan and the Soviet Union are mentioned, and a two-year US study of heavy ion fusion electric power plants is summarized. (orig.)

  7. Issues and opportunities: beam simulations for heavy ion fusion

    International Nuclear Information System (INIS)

    UCRL- JC- 134975 PREPRINT code offering 3- D, axisymmetric, and ''transverse slice'' (steady flow) geometries, with a hierarchy of models for the ''lattice'' of focusing, bending, and accelerating elements. Interactive and script- driven code steering is afforded through an interpreter interface. The code runs with good parallel scaling on the T3E. Detailed simulations of machine segments and of complete small experiments, as well as simplified full- system runs, have been carried out, partially benchmarking the code. A magnetoinductive model, with module impedance and multi- beam effects, is under study. experiments, including an injector scalable to multi- beam arrays, a high- current beam transport and acceleration experiment, and a scaled final- focusing experiment. These ''phase I'' projects are laying the groundwork for the next major step in HIF development, the Integrated Research Experiment (IRE). Simulations aimed directly at the IRE must enable us to: design a facility with maximum power on target at minimal cost; set requirements for hardware tolerances, beam steering, etc.; and evaluate proposed chamber propagation modes. Finally, simulations must enable us to study all issues which arise in the context of a fusion driver, and must facilitate the assessment of driver options. In all of this, maximum advantage must be taken of emerging terascale computer architectures, requiring an aggressive code development effort. An organizing principle should be pursuit of the goal of integrated and detailed source- to- target simulation. methods for analysis of the beam dynamics in the various machine concepts, using moment- based methods for purposes of design, waveform synthesis, steering algorithm synthesis, etc. Three classes of discrete- particle models should be coupled: (1) electrostatic/ magnetoinductive PIC simulations should track the beams from the source through the final- focusing optics, passing details of the time- dependent distribution function to

  8. Issues and opportunities: beam simulations for heavy ion fusion

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, A

    1999-07-15

    UCRL- JC- 134975 PREPRINT code offering 3- D, axisymmetric, and ''transverse slice'' (steady flow) geometries, with a hierarchy of models for the ''lattice'' of focusing, bending, and accelerating elements. Interactive and script- driven code steering is afforded through an interpreter interface. The code runs with good parallel scaling on the T3E. Detailed simulations of machine segments and of complete small experiments, as well as simplified full- system runs, have been carried out, partially benchmarking the code. A magnetoinductive model, with module impedance and multi- beam effects, is under study. experiments, including an injector scalable to multi- beam arrays, a high- current beam transport and acceleration experiment, and a scaled final- focusing experiment. These ''phase I'' projects are laying the groundwork for the next major step in HIF development, the Integrated Research Experiment (IRE). Simulations aimed directly at the IRE must enable us to: design a facility with maximum power on target at minimal cost; set requirements for hardware tolerances, beam steering, etc.; and evaluate proposed chamber propagation modes. Finally, simulations must enable us to study all issues which arise in the context of a fusion driver, and must facilitate the assessment of driver options. In all of this, maximum advantage must be taken of emerging terascale computer architectures, requiring an aggressive code development effort. An organizing principle should be pursuit of the goal of integrated and detailed source- to- target simulation. methods for analysis of the beam dynamics in the various machine concepts, using moment- based methods for purposes of design, waveform synthesis, steering algorithm synthesis, etc. Three classes of discrete- particle models should be coupled: (1) electrostatic/ magnetoinductive PIC simulations should track the beams from the source through the final- focusing optics

  9. The concept of a research fusion reactor

    International Nuclear Information System (INIS)

    Thus,for advancement towards a commercial fusion reactor,we have proposed here as a next step a steady state operated research fusion reactor with an increased plasma-wall detachment so as to further guarantee not only the production but also a long-term (for many years) confinement of a self-sustained plasma at the existing technology level. We consider the primary goal of the research fusion reactor is the provision of full-scale conditions for carrying out materials science experiments to create and test 1 st wall materials for the commercial fusion reactor

  10. The status of nuclear fusion research

    International Nuclear Information System (INIS)

    The author summarizes the status of nuclear fusion research as follows: scientific feasibility of a fusion reactor can be demonstrated in 3-6 years; large scale (future) experiments are needed to test engineering problems, etc., possibly in 1990; economical questions are becoming important. There are two aspects: the energy cost must be sufficiently low (absolute), and the fusion reactor cost should be competitive with indigenous energy sources (relative); and possible alternatives to improve the economical aspects of a CTR must be explored

  11. Accelerator ampersand Fusion Research Division: 1993 Summary of activities

    International Nuclear Information System (INIS)

    The Accelerator and Fusion Research Division (AFRD) is not only one of the largest scientific divisions at LBL, but also the one of the most diverse. Major efforts include: (1) investigations in both inertial and magnetic fusion energy; (2) operation of the Advanced Light Source, a state-of-the-art synchrotron radiation facility; (3) exploratory investigations of novel radiation sources and colliders; (4) research and development in superconducting magnets for accelerators and other scientific and industrial applications; and (5) ion beam technology development for nuclear physics and for industrial and biomedical applications. Each of these topics is discussed in detail in this book

  12. Accelerator & Fusion Research Division: 1993 Summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    Chew, J.

    1994-04-01

    The Accelerator and Fusion Research Division (AFRD) is not only one of the largest scientific divisions at LBL, but also the one of the most diverse. Major efforts include: (1) investigations in both inertial and magnetic fusion energy; (2) operation of the Advanced Light Source, a state-of-the-art synchrotron radiation facility; (3) exploratory investigations of novel radiation sources and colliders; (4) research and development in superconducting magnets for accelerators and other scientific and industrial applications; and (5) ion beam technology development for nuclear physics and for industrial and biomedical applications. Each of these topics is discussed in detail in this book.

  13. Is fusion research worth it?

    International Nuclear Information System (INIS)

    Long-term energy R and D such as fusion needs to be valued in the framework of options analysis. The R and D itself does not provide energy, but rather provides the option to construct and operate energy-producing systems. An initial analysis of this problem applied the Black-Scholes formula based on historical fluctuations in the cost of energy. That study concluded that for reasonable assumptions about the operating cost of fusion power plants, the fusion option was cost effective. Here we use a simpler and more transparent estimate of the future value of energy, but look more carefully at the question of the opportunity cost of engaging in fusion R and D, including the possibility of hedging financially against increased prices for acceptable energy through an 'energy insurance' fund, as compared with the fusion option. We find that the fusion option is very attractive if the probability is more than a few percent that fusion will cost less than the best environmentally acceptable alternative for its potential market share. (author)

  14. Optimization of ion sources for controlled fusion research applications

    International Nuclear Information System (INIS)

    The prospect for improvements in the performance of ion sources for controlled fusion research applications is investigated from a theoretical point of view. The objectives are identified in terms of beam energy, intensity, purity and power efficiency. By analyzing the process in the extraction and formation of an ion beam, an expression is obtained which relates the parameters of the ion source to the quality of the beam. The implications of the result in improving the performance of the ion source for CTR applications is discussed

  15. Fusion Research in Ioffe Institute

    Science.gov (United States)

    Askinazi, L. G.; Afanasyev, V. I.; Altukhov, A. B.; Bakharev, N. N.; Belokurov, A. A.; Bulanin, V. V.; Bykov, A. S.; Chernyshev, F. V.; Chugunov, I.; Dyachenko, V. V.; Esipov, L. A.; Gin, D.; Goncharov, P. R.; Gurchenko, A. D.; Gusakov, E. Z.; Gusev, V. K.; Heuraux, S.; Iblyaminova, A. D.; Irzak, M. A.; Kantor, M. Yu.; Kaveeva, E. G.; Kiviniemi, T.; Khilkevitch, E. M.; Khitrov, S. A.; Khromov, N. A.; Kornev, V. A.; Kouprienko, D. V.; Kurskiev, G. S.; Lashkul, S. I.; Lebedev, S. V.; Leerink, S.; Melnik, A. D.; Minaev, V. B.; Mironov, M. I.; Miroshnikov, I. V.; Mukhin, E. E.; Nesenevich, V. G.; Niskala, P.; Novokhatsky, A. N.; Patrov, M. I.; Perevalov, A. A.; Petrov, M. P.; Petrov, A. V.; Petrov, Yu. V.; Popov, A. Yu.; Rozhansky, V. A.; Rozhdestvenskiy, V. V.; Sakharov, N. V.; Saveliev, A. N.; Senichenkov, I. Yu.; Sergeev, V. Yu.; Shchegolev, P. B.; Shatalin, S. V.; Shcherbinin, O. N.; Shevelev, A. E.; Sidorov, A. V.; da Silva, F.; Smirnov, A. I.; Stepanov, A. Yu.; Sysoeva, E. V.; Teplova, N. V.; Tolstyakov, S. Yu.; Tukachinsky, A. S.; Varfolomeev, V. I.; Vekshina, E. O.; Vildjunas, M. I.; Voronin, A. V.; Voskoboinikov, S. P.; Wagner, F.; Yashin, A. Yu.; Zhubr, N. A.

    2015-10-01

    In this paper we present the fusion related activities of the Plasma Physics Division at the Ioffe Institute. The first experiments on lower hybrid current drive (LHCD) in a spherical tokamak performed at the Globus-M tokamak (R = 0.36 m, a = 0.24 m, Bt = 0.4 T, Ip = 200 kA) with a novel poloidally oriented grill resulted in an RF driven current of up to 30 kA at (100 kW, 2.5 GHz), exceeding the modelling predictions. At the FT-2 tokamak (R = 0.56 m, a = 0.08 m, Bt = 3 T, Ip = 30 kA) experiments with a traditional toroidally oriented grill revealed no strong dependence of the LHCD density limit on the H/D ratio in spite of LH resonance densities differing by a factor of 3. Microwave Doppler reflectometry (DR) at the Globus-M, and DR and heavy ion beam probe measurements at the tokamak TUMAN-3M (R = 0.53 m, a = 0.24 m, Bt = 1.0 T, Ip = 190 kA) demonstrated geodesic acoustic mode (GAM) suppression at the L to H transition. Observations at FT-2 using Doppler Enhanced Scattering showed that the GAM amplitude is anti-correlated both spatially and temporally to the drift turbulence level and electron thermal diffusivity. For the first time turbulence amplitude modulation at the GAM frequency was found both experimentally and in global gyrokinetic modelling. A model of the L-H transition is proposed based on this effect. The loss mechanisms of energetic ions' (EI) were investigated in the neutral beam injection (NBI) experiments on Globus-M and TUMAN-3M. Empirical scaling of the 2.45 MeV DD neutron rate for the two devices shows a strong dependence on toroidal field Bt1.29 and plasma current Ip1.34 justifying the Bt and Ip increase by a factor of 2.5 for the proposed upgrade of Globus-M. Bursts of ˜1 MHz Alfvenic type oscillations correlating with sawtooth crashes were observed in ohmic TUMAN-3M discharges. The possibility of low threshold parametric excitation of Bernstein and upper hybrid waves trapped in drift-wave eddies resulting in anomalous absorption in electron

  16. Heavy ion beam propagation through a gas-filled chamber for inertial confinement fusion

    International Nuclear Information System (INIS)

    The work presented here evaluates the dynamics of a beam of heavy ions propagating through a chamber filled with gas. The motivation for this research stems from the possibility of using heavy ion beams as a driver in inertial confinement fusion reactors for the purpose of generating electricity. Such a study is important in determining the constraints on the beam which limit its focus to the small radius necessary for the ignition of thermonuclear microexplosions which are the source of fusion energy. Nuclear fusion is the process of combining light nuclei to form heavier ones. One possible fusion reaction combines two isotopes of hydrogen, deuterium and tritium, to form an alpha particle and a neutron, with an accompanying release of ∼17.6 MeV of energy. Generating electricity from fusion requires that we create such reactions in an efficient and controlled fashion, and harness the resulting energy. In the inertial confinement fusion (ICF) approach to energy production, a small spherical target, a few millimeters in radius, of deuterium and tritium fuel is compressed so that the density and temperature of the fuel are high enough, ∼200 g/cm3 and ∼20 keV, that a substantial number of fusion reactions occur; the pellet microexplosion typically releases ∼350 MJ of energy in optimized power plant scenarios

  17. Heavy ion beam propagation through a gas-filled chamber for inertial confinement fusion

    Energy Technology Data Exchange (ETDEWEB)

    Barboza, N.O.

    1996-10-01

    The work presented here evaluates the dynamics of a beam of heavy ions propagating through a chamber filled with gas. The motivation for this research stems from the possibility of using heavy ion beams as a driver in inertial confinement fusion reactors for the purpose of generating electricity. Such a study is important in determining the constraints on the beam which limit its focus to the small radius necessary for the ignition of thermonuclear microexplosions which are the source of fusion energy. Nuclear fusion is the process of combining light nuclei to form heavier ones. One possible fusion reaction combines two isotopes of hydrogen, deuterium and tritium, to form an alpha particle and a neutron, with an accompanying release of {approximately}17.6 MeV of energy. Generating electricity from fusion requires that we create such reactions in an efficient and controlled fashion, and harness the resulting energy. In the inertial confinement fusion (ICF) approach to energy production, a small spherical target, a few millimeters in radius, of deuterium and tritium fuel is compressed so that the density and temperature of the fuel are high enough, {approximately}200 g/cm{sup 3} and {approximately}20 keV, that a substantial number of fusion reactions occur; the pellet microexplosion typically releases {approximately}350 MJ of energy in optimized power plant scenarios.

  18. Diagnostic neutral beams for plasma studies in magnetic fusion devices

    International Nuclear Information System (INIS)

    Nowadays, low-divergent, quasi-stationary neutral beams are widely used in magnetic fusion devices as a diagnostic tool providing unique information about plasma parameters. Essentially, a diagnostic determines the requirements for the beams, which in many cases consist in sufficiently large current density and energy of the particles so that the beam can penetrate to the plasma core. At the same time, the duration of the beams should overlap that of a plasma shot (∼10 s or longer for large machines). We have developed a number of diagnostic hydrogen beams with a maximum beam energy of 55kV, extracted ion current varying up to 6 A, and pulse duration from several milliseconds to 10 s. The beams are formed by a four electrode ion optical system which makes it possible to provide a low divergent (0.5-0.7 deg.) beam. Additionally, a beam can be focused onto a desired point by proper choice of the curvature radius of the grids. The beams can be modulated with a frequency variable up to 500 Hz. The plasma emitter in the injector is provided by a radiofrequency discharge in hydrogen (deuterium) for long duration beams and, alternatively, by an arc-discharge plasma box for the beams with a duration of up to ∼0.5 s. The arc discharge plasma box provides a higher proton fraction (∼90%) than the RF discharge version (∼60%). The parameters for the different beams developed are presented. (author)

  19. Developing high brightness beams for heavy ion driven inertial fusion

    OpenAIRE

    Kwan, J.W.; Ahle, L.A.; Anders, A; Bieniosek, F.M.; Chacon-Golcher, E.; Grote, D. P.; Henestroza, E.; Leung, K.N.; Molvik, A.W.

    2001-01-01

    Heavy ion fusion (HIF) drivers require large currents and bright beams. In this paper we review the two different approaches for building HIF injectors and the corresponding ion source requirements. The traditional approach uses large aperture, low current density ion sources, resulting in a very large injector system. A more recent conceptual approach merges high current density mini-beamlets into a large current beam in order to significantly reduce the size of the injector. Experimen...

  20. Study, analysis, design and diagnostics of plasma and beam facing components of fusion devices

    OpenAIRE

    Sartori, Emanuele

    2013-01-01

    Neutral Beam Injection is the horse-power of present and future fusion devices. Modeling plays a fundamental role in anticipating/predicting the performance of the injector and optimizing its behaviour. Successful design can only be achieved through integrated approach between physics and engineering. In the last three years, my research activity has been carried out at Consorzio RFX, where the ultimate neutral beam test facility is being designed and constructed. This PhD thesis has sought t...

  1. Accelerator system and final beam transport in heavy ion inertial confinement fusion

    International Nuclear Information System (INIS)

    Physical aspects of the fundamental components of accelerator system, beam and target for heavy ion inertial confinement fusion, are briefly reviewed. A particular emphasis is placed on the heavy ion transport in reactor vessel. The feasibility study at European research group on ignition by heavy ion driver is also presented. (author)

  2. Progress in bright ion beams for industry, medicine and fusion at LBNL

    International Nuclear Information System (INIS)

    Recent progresses at LBNL in developing ion beams for industry, radiation therapy and inertial fusion applications were discussed. The highlights include ion beam lithography, boron neutron capture therapy (BNCT), and heavy ion fusion (HIF) drivers using multiple linacs

  3. Comparison of activation in fission and fusion spectrum neutron beams

    International Nuclear Information System (INIS)

    The materials used in the construction of fusion reactors have to satisfy a number of criterions, one of the important being low activation due to neutron irradiation. Experimental analysis of the activation of candidate materials for the first wall is performed with the irradiation of samples in various neutron fields, frequently in the field of a fission reactor. In the present work a calculation is performed to compare the expected activation of candidate materials intended to be used for the first wall in fusion reactors with the activation of a sample of the same material in a fission reactor beam. The FISPACT code is used for activation calculations. An investigation, to what extent the results of activation in a fission spectrum neutron beam, where most neutrons have energies of less than 2 MeV, mimic the real situation in a fusion reactor with the peak neutron energy around 14 MeV, is performed. (author)

  4. Future directions in inertial fusion research

    International Nuclear Information System (INIS)

    The inertial fusion has undergone profound changes over the years, while maintaining a remarkable degree of stability and continuity of purpose. In the early seventies, the program had two goals, near-term military and long-term civilian power applications. With the perception that oil is plentiful, the present Administration's attitude towards development of new energy sources shifted. But, the goals of inertial fusion have remained constant. Indeed, they have been useful spinoffs in both military and civilian areas such as laboratory x-ray laser experiments, which could have biomedical applications, and development of high energy beam physics with application to the Strategic Defense initiative

  5. The development of laser fusion research

    International Nuclear Information System (INIS)

    Laser fusion research started soon after the invention of laser. In 1972, the research was declassified and nuclear fusion by laser inplosion was proposed by J. Nuckolls. Since then, 26 years has passed and laser implosion experiments demonstrated 1000 times solid density compression. By the demonstration of 1000 times solid density, the mission of the laser fusion research shifted from 'implosion physics' to 'ignition and high gain', namely demonstration of fusion output of 100 times input laser energy. By the recent developments of laser technology, ultra intense laser became available and opened up a new ignition scheme which is called 'Fast Ignition'. The technology for the diode pumped solid state laser (DPSSL) is developed toward a laser driver for reactor. U.S. and France are constructing MJ lasers for demonstrating ignition and burn and Osaka University is investigating the fast ignition and the equivalent plasma of confinement (EPOC) toward high gain. (author)

  6. Magnetized Target Fusion in Advanced Propulsion Research

    Science.gov (United States)

    Cylar, Rashad

    2003-01-01

    The Magnetized Target Fusion (MTF) Propulsion lab at NASA Marshall Space Flight Center in Huntsville, Alabama has a program in place that has adopted to attempt to create a faster, lower cost and more reliable deep space transportation system. In this deep space travel the physics and development of high velocity plasma jets must be understood. The MTF Propulsion lab is also in attempt to open up the solar system for human exploration and commercial use. Fusion, as compared to fission, is just the opposite. Fusion involves the light atomic nuclei combination to produce denser nuclei. In the process, the energy is created by destroying the mass according to the distinguished equation: E = mc2 . Fusion energy development is being pursued worldwide as a very sustainable form of energy that is environmentally friendly. For the purposes of space exploration fusion reactions considered include the isotopes of hydrogen-deuterium (D2) and tritium (T3). Nuclei have an electrostatic repulsion between them and in order for the nuclei to fuse this repulsion must be overcome. One technique to bypass repulsion is to heat the nuclei to very high temperatures. The temperatures vary according to the type of reactions. For D-D reactions, one billion degrees Celsius is required, and for D-T reactions, one hundred million degrees is sufficient. There has to be energy input for useful output to be obtained form the fusion To make fusion propulsion practical, the mass, the volume, and the cost of the equipment to produce the reactions (generally called the reactor) need to be reduced by an order of magnitude or two from the state-of-the-art fusion machines. Innovations in fusion schemes are therefore required, especially for obtaining thrust for propulsive applications. Magnetized target fusion (MTF) is one of the innovative fusion concepts that have emerged over the last several years. MSFC is working with Los Alamos National Laboratory and other research groups in studying the

  7. Report on the cooperating researches utilizing fusion engineering facilities completed in the fiscal year 2007 (Joint research)

    International Nuclear Information System (INIS)

    The Division of Fusion Energy Technology of the Fusion Research and Development Directorate is carrying out cooperating researches with universities, research institutes and industries using five fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), MeV Test Facility (MTF), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS). In the fiscal year 2007 (from April 1, 2007 to March 31, 2008), 24 activities were carried out as the cooperating researches. This report reviews the results of 8 activities which were completed in the fiscal year 2007. (author)

  8. Report on the cooperating researches utilizing fusion engineering facilities completed in the fiscal year 2008 (Joint research)

    International Nuclear Information System (INIS)

    The Division of Fusion Energy Technology of the Fusion Research and Development Directorate is carrying out cooperating researches with universities, research institutes and industries using five fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS). In the fiscal year 2007 (from April 1, 2008 to March 31, 2009), 19 activities were carried out as the cooperating researches. This report reviews the results of 8 activities which were completed in the fiscal year 2008. (author)

  9. Beam dynamics analysis in pulse compression using electron beam compact simulator for Heavy Ion Fusion

    Directory of Open Access Journals (Sweden)

    Kikuchi Takashi

    2013-11-01

    Full Text Available In a final stage of an accelerator system for heavy ion inertial fusion (HIF, pulse shaping and beam current increase by bunch compression are required for effective pellet implosion. A compact simulator with an electron beam was constructed to understand the beam dynamics. In this study, we investigate theoretically and numerically the beam dynamics for the extreme bunch compression in the final stage of HIF accelerator complex. The theoretical and numerical results implied that the compact experimental device simulates the beam dynamics around the stagnation point for initial low temperature condition.

  10. Stellarator fusion neutronics research in Australia

    International Nuclear Information System (INIS)

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

  11. Illumination non-uniformity of spirally wobbling beam in heavy ion fusion

    Science.gov (United States)

    Suzuki, T.; Noguchi, K.; Kurosaki, T.; Barada, D.; Kawata, S.; Ma, Y. Y.; Ogoyski, A. I.

    2016-03-01

    In inertial confinement fusion, the driver beam illumination non-uniformity leads a degradation of fusion energy output. The illumination non-uniformity allowed is less than a few percent in inertial fusion target implosion. Heavy ion beam (HIB) accelerator provides a capability to oscillate a beam axis with a high frequency. The wobbling beams may provide a new method to reduce or smooth the beam illumination non-uniformity. In this paper the HIBs wobbling illumination scheme was optimized.

  12. Ion beams in nuclear fusion with inertial confinement - fundamentals

    International Nuclear Information System (INIS)

    For a long-term solution of the energy problem the different technical concepts of thermonuclear fusion, dependent on their implementation chances, meet with ever greater interest worldwide. In this connection the fusion of light atomic nuclei with inertial confinement is considered a promising alternative as compared to the fusion with magnetic confinement of the hot plasma. Already more than ten years ago extensive investigations had started on the use of lasers and electrons as inducing radiation; and for about ten years now intensive experimental and theoretical works as well as technological studies have been carried out concerning the ignition of a thermonuclear fuel enclosed in a pellet through highly intense, pulsed and sharply focused beams of light and heavy ions

  13. Beam simultaneity results in the Helios laser fusion facility

    International Nuclear Information System (INIS)

    The operation of the beam simultaneity system of the 10-kJ, 20-TW, eight-beam Helios CO2 laser experimental fusion facility, which is required to ensure that the eight laser beams arrive at the target within 33 picosec of each other, is discussed. The system measures relative beam path lengths with a resolution of 1 mm based on the comparison of electro-optically modulated signals from a CW CO2 laser injected into the eight beam paths and a reference path and reflected off a reflecting sphere in the target chamber. Signal-to-electrical-noise and signal-to-optical-noise ratios are both greater than 500, with the noise composed of components at 1 and 0.1 Hz in both the reference and beam paths. It is estimated that each optical beam path can be measured to within 3 mm, and that the system can be realigned with less than 3 mm path change. Beam simultaneity is finally limited by dispersive and dynamical effects of the gain medium of the triple pass power amplifiers, which have not yet been measured, but are believed to be compatible with the goal accuracy (10 picosec) and resolution (33 picosec) of the system

  14. Technical review of the Sandia Laboratories' Particle Beam Fusion Program

    International Nuclear Information System (INIS)

    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

  15. Numerical study of neutron beam divergence in a beam-fusion scenario employing laser driven ions

    Science.gov (United States)

    Alejo, A.; Green, A.; Ahmed, H.; Robinson, A. P. L.; Cerchez, M.; Clarke, R.; Doria, D.; Dorkings, S.; Fernandez, J.; McKenna, P.; Mirfayzi, S. R.; Naughton, K.; Neely, D.; Norreys, P.; Peth, C.; Powell, H.; Ruiz, J. A.; Swain, J.; Willi, O.; Borghesi, M.; Kar, S.

    2016-09-01

    The most established route to create a laser-based neutron source is by employing laser accelerated, low atomic-number ions in fusion reactions. In addition to the high reaction cross-sections at moderate energies of the projectile ions, the anisotropy in neutron emission is another important feature of beam-fusion reactions. Using a simple numerical model based on neutron generation in a pitcher-catcher scenario, anisotropy in neutron emission was studied for the deuterium-deuterium fusion reaction. Simulation results are consistent with the narrow-divergence (∼ 70 ° full width at half maximum) neutron beam recently served in an experiment employing multi-MeV deuteron beams of narrow divergence (up to 30° FWHM, depending on the ion energy) accelerated by a sub-petawatt laser pulse from thin deuterated plastic foils via the Target Normal Sheath Acceleration mechanism. By varying the input ion beam parameters, simulations show that a further improvement in the neutron beam directionality (i.e. reduction in the beam divergence) can be obtained by increasing the projectile ion beam temperature and cut-off energy, as expected from interactions employing higher power lasers at upcoming facilities.

  16. Magnetic confinement fusion energy research

    Energy Technology Data Exchange (ETDEWEB)

    Grad, H

    1977-03-01

    Controlled Thermonuclear Fusion offers probably the only relatively clean energy solution with completely inexhaustible fuel and unlimited power capacity. The scientific and technological problem consists in magnetically confining a hot, dense plasma (pressure several to hundreds of atmospheres, temperature 10/sup 8/ degrees or more) for an appreciable fraction of a second. The scientific and mathematical problem is to describe the behavior, such as confinement, stability, flow, compression, heating, energy transfer and diffusion of this medium in the presence of electromagnetic fields just as we now can for air or steam. Some of the extant theory consists of applications, routine or ingenious, of known mathematical structures in the theory of differential equations and in traditional analysis. Other applications of known mathematical structures offer surprises and new insights: the coordination between sub-supersonic and elliptic-hyperbolic is fractured; supersonic propagation goes upstream; etc. Other completely nonstandard mathematical structures with significant theory are being rapidly uncovered (and somewhat less rapidly understood) such as non-elliptic variational equations and new types of weak solutions. It is these new mathematical structures which one should expect to supply the foundation for the next generation's pure mathematics, if history is a guide. Despite the substantial effort over a period of some twenty years, there are still basic and important scintific and mathematical discoveries to be made, lying just beneath the surface.

  17. Magnetic confinement fusion energy research

    International Nuclear Information System (INIS)

    Controlled Thermonuclear Fusion offers probably the only relatively clean energy solution with completely inexhaustible fuel and unlimited power capacity. The scientific and technological problem consists in magnetically confining a hot, dense plasma (pressure several to hundreds of atmospheres, temperature 108 degrees or more) for an appreciable fraction of a second. The scientific and mathematical problem is to describe the behavior, such as confinement, stability, flow, compression, heating, energy transfer and diffusion of this medium in the presence of electromagnetic fields just as we now can for air or steam. Some of the extant theory consists of applications, routine or ingenious, of known mathematical structures in the theory of differential equations and in traditional analysis. Other applications of known mathematical structures offer surprises and new insights: the coordination between sub-supersonic and elliptic-hyperbolic is fractured; supersonic propagation goes upstream; etc. Other completely nonstandard mathematical structures with significant theory are being rapidly uncovered (and somewhat less rapidly understood) such as non-elliptic variational equations and new types of weak solutions. It is these new mathematical structures which one should expect to supply the foundation for the next generation's pure mathematics, if history is a guide. Despite the substantial effort over a period of some twenty years, there are still basic and important scintific and mathematical discoveries to be made, lying just beneath the surface

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

    International Nuclear Information System (INIS)

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

  19. Electron beam welding using fusion and cold wire fill

    International Nuclear Information System (INIS)

    A straight-fusion (self-filler) welding technique generally poses no problem for electron beam welding. However, where control of penetration is a critical item and burn-through cannot be tolerated, this technique may not be satisfactory. To assure against beam-spike burn-through on a 1/4-inch deep weld joint, a low-power root-fusion pass, supplemented by numerous filler passes, was selected. However, this technique proved to have numerous problems. Voiding and porosity showed frequently in the first applications of this cold-wire filler process. Taper-out cratering, bead-edge undercutting, and spatter were also problems. These imperfections, however, were overcome. Employment of a circle generator provided the necessary heating of the joint walls to eliminate voids. The moving beam spot also provided a stirring action, lessening porosity. Taper-out cratering was eliminated by adjusting the timing of the current cutoff and wire-feed cutoff. Undercutting, bead height, and spatter were controlled by beam defocus

  20. Outline of heavy ion beam accelerator for inertial confinement fusion

    International Nuclear Information System (INIS)

    Heavy ion inertial fusion program has become more promising through the intense works on high energy, heavy ion accelerators during past four years. The heavy iron method is superior to the methods with other particle beam, because the peak current requirement is reduced drastically to several kA. The driver efficiency is expected to be 20% or more in the heavy ion method, and the absorption efficiency in the pellets is three times as high as that of laser fusion method. In Japan, Institute of Plasma Physics of Nagoya University and Institute of Laser Engineering of Osaka University participate mainly in the design of reactor and pellet systems, while National Laboratory for High Energy Physics and Institute for Nuclear Study of University of Tokyo have studied on heavy ion accelerators. In this paper, the outline of the accelerator system is described on the basis of the typical parameters of pellet design. The determination of beam parameters, the beam lines in reactors, current multiplication, the main parameters of the storage ring, the ion source and the linear accelerator are explained. In the present design concept, an RFQ linac is proposed in low velocity region. The focus action is independent of the beam velocity, and it has the capture efficiency as high as about 90%. (Kako, I.)

  1. Simulations of longitudinal beam dynamics of space-charge dominated beams for heavy ion fusion

    International Nuclear Information System (INIS)

    The longitudinal instability has potentially disastrous effects on the ion beams used for heavy ion driven inertial confinement fusion. This instability is a open-quotes resistive wallclose quotes instability with the impedance coining from the induction modules in the accelerator used as a driver. This instability can greatly amplify perturbations launched from the beam head and can prevent focusing of the beam onto the small spot necessary for fusion. This instability has been studied using the WARPrz particle-in-cell code. WARPrz is a 2 1/2 dimensional electrostatic axisymmetric code. This code includes a model for the impedance of the induction modules. Simulations with resistances similar to that expected in a driver show moderate amounts of growth from the instability as a perturbation travels from beam head to tail as predicted by cold beam fluid theory. The perturbation reflects off the beam tail and decays as it travels toward the beam head. Nonlinear effects cause the perturbation to steepen during reflection. Including the capacitive component of the, module impedance. has a partially stabilizing effect on the longitudinal instability. This reduction in the growth rate is seen in both cold beam fluid theory and in simulations with WARPrz. Instability growth rates for warm beams measured from WARPrz are lower than cold beam fluid theory predicts. Longitudinal thermal spread cannot account for this decrease in the growth rate. A mechanism for coupling the transverse thermal spread to decay of the longitudinal waves is presented. The longitudinal instability is no longer a threat to the heavy ion fusion program. The simulations in this thesis have shown that the growth rate for this instability will not be as large as earlier calculations predicted

  2. Inertial fusion with heavy ion beams

    International Nuclear Information System (INIS)

    This article presents the status of present activities and considerations on future perspectives. It is organized as follows: After a short presentation of basic facts, the accelerator issues will be discussed, followed by a short description of a reactor concept and a discussion of target problems. Many theoretical studies and some experimental developments made during the past five years have increased our knowledge on specific accelerator and reactor issues and - as a spin-off of these results - have improved the performance of existing accelerator facilities. The direction for continued research in the near future has become an important question and is now being critically examined for planning further programs. The last chapter deals with these considerations for developing facilities which should enable experimental investigations of accelerator and target problems. (orig.)

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

    International Nuclear Information System (INIS)

    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/cm2. 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

  4. Ion movie camera for particle-beam-fusion experiments

    International Nuclear Information System (INIS)

    A camera with a 3 ns time resolution and a continuous (>100 ns) record length has been developed to image a 1012--1013 W/cm2 ion beam for inertial-confinement-fusion experiments. A thin gold Rutherford-scattering foil placed in the path of the beam scatters ions into the camera. The foil is in a near-optimized scattering geometry and reduces the beam intensity∼seven orders of magnitude. The scattered ions are pinhole imaged onto a 2D array of 39 p-i-n diode detectors; outputs are recorded on LeCroy 6880 transient-waveform digitizers. The waveforms are analyzed and combined to produce a 39-pixel movie which can be displayed on an image processor to provide time-resolved horizontal- and vertical-focusing information

  5. An ion movie camera for particle-beam-fusion experiments

    International Nuclear Information System (INIS)

    A camera with 3-ns time resolution -- and a continuous (> 100-ns) record length -- has been developed to image a 1012-1013 W/cm2 ion beam for inertial-confinement-fusion experiments. A thin gold Rutherford-scattering foil placed in the path of the beam scatters ions into the camera. The foil is in a near-optimized scattering geometry and reduces the beam intensity seven orders of magnitude. The scattered ions are pinhole imaged onto a 2-D array of 39 p-i-n diode detectors. The output of each detector is recorded on a LeCroy 6880 transient-waveform digitizer. The waveforms are analyzed and combined to produce a 39-pixel movie which can be displayed on an image processor to provide, for example, time-resolved horizontal- and vertical-focusing information

  6. Spiraling Beam Illumination Uniformity on Heavy Ion Fusion Target

    CERN Document Server

    Kurosaki, T; Noguchi, K; Koseki, S; Barada, D; Ma, Y Y; Ogoyski, A I; Barnard, J J; Logan, B G

    2012-01-01

    A few percent wobbling-beam illumination nonuniformity is realized in heavy ion inertial confinement fusion (HIF) by a spiraling beam axis motion in the paper. So far the wobbling heavy ion beam (HIB) illumination was proposed to realize a uniform implosion in HIF. However, the initial imprint of the wobbling HIBs was a serious problem and introduces a large unacceptable energy deposition nonuniformity. In the wobbling HIBs illumination, the illumination nonuniformity oscillates in time and space. The oscillating-HIB energy deposition may contribute to the reduction of the HIBs illumination nonuniformity. The wobbling HIBs can be generated in HIB accelerators and the oscillating frequency may be several 100MHz-1GHz. Three-dimensional HIBs illumination computations presented here show that the few percent wobbling HIBs illumination nonuniformity oscillates successfully with the same wobbling HIBs frequency.

  7. Longitudinal beam dynamics for heavy ion fusion using WARPrz

    International Nuclear Information System (INIS)

    WARPrz is a 2.5 dimensional, cylindrically symmetric, electrostatic, particle-in-cell code. It is part of the WARP family of codes which has been developed to study heavy ion fusion driver issues. WARPrz is being used to study the longitudinal dynamics of heavy ion beams including a longitudinal instability that is driven by the impedance of the LINAC accelerating modules. This instability is of concern because it can enhance longitudinal momentum spread; chromatic abhoration in the lens system restricts the amount of momentum spread allowed in the beam in the final focusing system. The impedance of the modules is modeled by a continuum of resistors and capacitors in parallel in WARPrz. We discuss simulations of this instability including the effect of finite temperature and reflection of perturbations off the beam ends. We also discuss intermittency of axial confining fields (''ears'' fields) as a seed for this instability

  8. Inertial confinement fusion research in Japan

    International Nuclear Information System (INIS)

    Inertial confinement fusion is now popular again. In Europe, several institutes become very active. Japan, the US and the USSR continue their efforts on ICF. The research objectives of Japan is completely dedicated for the energy production to the peaceful use. The most developed data in the author's works are presented

  9. Maryland controlled fusion research program

    International Nuclear Information System (INIS)

    In this paper, we summarize the technical progress in four major areas of tokamak research: (a) L/H transition and edge turbulence and transport; (b) active control of microturbulence and transport; (c) major disruptions; and (d) the sawtooth crash

  10. Current trends in laser fusion driver and beam combination laser systems using stimulated Brillouin scattering phase conjugate mirrors for a fusion driver

    International Nuclear Information System (INIS)

    Laser facilities in the world have been developing flash-lamp-pumped ultrahigh-energy solid-state lasers for fusion research and high-repetition diode-pumped solid-state lasers to act as commercial fusion drivers. A commercial laser fusion driver requires a high-energy beam with a total energy of several megajoules per pulse in several nanoseconds with a ∼10-Hz repetition rate. However, current laser technologies have limitations in raising the beam energy when operating with a high repetition rate, which is necessary for a commercial fusion driver to function properly. The beam combination laser system, which that uses stimulated Brillouin scattering phase conjugate mirrors, is a promising candidate for a fusion driver because it can obtain both a high energy and a high repetition rate with separate amplifications. For the realization of the beam combination laser system, a self-phase control technique was proposed for the coherent beam combined output, and its principle was demonstrated experimentally.

  11. Intense metal ion beam source for heavy ion fusion

    International Nuclear Information System (INIS)

    We have developed an ion source which can produce high current beams of metal ions. The source uses a metal vapor vacuum arc discharge as the plasma medium from which the ions are extracted, so we have called this source the MEVVA ion source. The metal plasma is created simply and efficiently and no carrier gas is required. Beams have been produced from metallic elements spanning the periodic table from lithium through uranium, at extraction voltages from 10 to 60 kV and with beam currents as high as 1.1 Amperes (electrical current in all charge states). A brief description of the source is given and its possible application as an ion source for heavy ion fusion is considered. Beams such as C+ (greater than or equal to99% of the beam in this species and charge state), Cr2+ (80%), and Ta/sup 3+,4+,5+/ (mixed charge states) have been produced. Beam emittance measurements and ways of increasing the source brightness are discussed

  12. Plasma physics and nuclear fusion research

    CERN Document Server

    Gill, Richard D

    1981-01-01

    Plasma Physics and Nuclear Fusion Research covers the theoretical and experimental aspects of plasma physics and nuclear fusion. The book starts by providing an overview and survey of plasma physics; the theory of the electrodynamics of deformable media and magnetohydrodynamics; and the particle orbit theory. The text also describes the plasma waves; the kinetic theory; the transport theory; and the MHD stability theory. Advanced theories such as microinstabilities, plasma turbulence, anomalous transport theory, and nonlinear laser plasma interaction theory are also considered. The book furthe

  13. Heavy Ion Fusion Accelerator Research (HIFAR)

    International Nuclear Information System (INIS)

    This report discusses the following topics: emittance variations in current-amplifying ion induction lina; transverse emittance studies of an induction accelerator of heavy ions; drift compression experiments on MBE-4 and related emittance; low emittance uniform- density Cs+ sources for heavy ion fusion accelerator studies; survey of alignment of MBE-4; time-of-flight dependence on the MBE-4 quadrupole voltage; high order calculation of the multiple content of three dimensional electrostatic geometries; an induction linac injector for scaled experiments; induction accelerator test module for HIF; longitudinal instability in HIF beams; and analysis of resonant longitudinal instability in a heavy ion induction linac

  14. Belgian research on fusion beryllium waste

    International Nuclear Information System (INIS)

    Future fusion power plants will generate important quantities of neutron irradiated beryllium. Although recycling is the preferred management option for this waste, this may not be technically feasible for all of the beryllium, because of its radiological characteristics. Therefore, at SCK·CEN, we initiated a research programme aimed at studying aspects of the disposal of fusion beryllium, including waste characterisation, waste acceptance criteria, conditioning methods, and performance assessment. One of the main issues to be resolved is the development of fusion-specific waste acceptance criteria for surface or deep geological disposal, in particular with regard to the tritium content. In case disposal is the only solution, critical nuclides can be immobilised by conditioning the waste. As a first approach to immobilising beryllium waste, we investigated the vitrification of beryllium. Corrosion tests were performed on both metallic and vitrified beryllium to provide source data for performance assessment. Finally, a first step in performance assessment was undertaken. (author)

  15. Post-doctoral research work developed at the National Institute for Fusion Science - Japan

    International Nuclear Information System (INIS)

    This is a research report report on the work developed at the National Institute for Fusion Science - Japan, involving study of Beam Emission Spectroscopy. It describes the use of a fast neutral lithium beam (8 KeV) to measure the density profile in a Compact Helical Device. (A.C.A.S.)

  16. Status of light ion inertial fusion research at NRL

    International Nuclear Information System (INIS)

    This chapter reports on the use of high-brightness proton beams, extracted from axial pinch-reflex diodes mounted on the Naval Research Laboratory (NRL) Gamble II generator, to study light ion inertial fusion. Topics covered include the modular approach, ion beam brightness studies, light-ion beam transport, final focusing, the single diode approach, the inductive storage approach, an energy loss experiment, and future plans. Analysis of a modular inertial confinement fusion (ICF) system using axial pinch-reflex diodes shows that an operational window for transport of light-ion species exists. A proof-of-principle experiment for the required final focusing cell was conducted on Gamble II. Preliminary experiments using vacuum inductive storage and plasma opening switches have demonstrated factorof-three pulse compressions, with corresponding power and voltage multiplications for pulse durations of interest to PBFA II. The stopping power of deuterons in hot plasmas was measured in other experiments. It is demonstrated that about 40% enhancement in stopping power over that in cold targets when the deuteron beam is focused on the target to about .25 MA/cm2. Includes 6 diagrams

  17. Electron-beam-excited gas laser research

    International Nuclear Information System (INIS)

    Net energy gain in laser fusion places requirements on the laser that are not realized by any existing laser. Utilization of relativistic electron beams (REB's), a relatively new source for the excitation of gas laser media, may lead to new lasers that could satisfy these requirements. Already REB's have been utilized to excite gas laser media and produce gas lasers that have not been produced as successfully any other way. Electron-beam-excitation has produced electronic-transition dimer lasers that have not yet been produced by any other excitation scheme (for example, Xe2/ sup *(1)/, Kr:O(21S)/sup 2/, KrF/sup *(3)/). In addition, REB's have initiated chemical reactions to produce HF laser radiation with unique and promising results. Relativistic-electron-beam gas-laser research is continuing to lead to new lasers with unique properties. Results of work carried out at Sandia Laboratories in this pioneering effort of electron-beam-excited-gas lasers are reviewed. (U.S.)

  18. Particle-beam-fusion progress report, July 1979 through December 1979

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The following chapters are included in this semi-annual progress report: (1) fusion target studies, (2) target experiments, (3) particle-beam source developments, (4) particle beam experiments, (5) pulsed power, (6) pulsed power applications, and (7) electron beam fusion accelerator project. (MOW)

  19. Particle-beam-fusion progress report, July 1979 through December 1979

    International Nuclear Information System (INIS)

    The following chapters are included in this semi-annual progress report: (1) fusion target studies, (2) target experiments, (3) particle-beam source developments, (4) particle beam experiments, (5) pulsed power, (6) pulsed power applications, and (7) electron beam fusion accelerator project

  20. The technology benefits of inertial confinement fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Powell, H T

    1999-05-26

    The development and demonstration of inertial fusion is incredibly challenging because it requires simultaneously controlling and precisely measuring parameters at extreme values in energy, space, and time. The challenges range from building megajoule (10{sup 6} J) drivers that perform with percent-level precision to fabricating targets with submicron specifications to measuring target performance at micron scale (10{sup {minus}6} m) with picosecond (10{sup {minus}12} s) time resolution. Over the past 30 years in attempting to meet this challenge, the inertial fusion community around the world has invented new technologies in lasers, particle beams, pulse power drivers, diagnostics, target fabrication, and other areas. These technologies have found applications in diverse fields of industry and science. Moreover, simply assembling the teams with the background, experience, and personal drive to meet the challenging requirements of inertial fusion has led to spin-offs in unexpected directions, for example, in laser isotope separation, extreme ultraviolet lithography for microelectronics, compact and inexpensive radars, advanced laser materials processing, and medical technology. The experience of inertial fusion research and development of spinning off technologies has not been unique to any one laboratory or country but has been similar in main research centers in the US, Europe, and Japan. Strengthening and broadening the inertial fusion effort to focus on creating a new source of electrical power (inertial fusion energy [IFE]) that is economically competitive and environmentally benign will yield rich rewards in technology spin-offs. The additional challenges presented by IFE are to make drivers affordable, efficient, and long-lived while operating at a repetition rate of a few Hertz; to make fusion targets that perform consistently at high-fusion yield; and to create target chambers that can repetitively handle greater than 100-MJ yields while producing minimal

  1. The technology benefits of inertial confinement fusion research

    International Nuclear Information System (INIS)

    The development and demonstration of inertial fusion is incredibly challenging because it requires simultaneously controlling and precisely measuring parameters at extreme values in energy, space, and time. The challenges range from building megajoule (106 J) drivers that perform with percent-level precision to fabricating targets with submicron specifications to measuring target performance at micron scale (10-6 m) with picosecond (10-12 s) time resolution. Over the past 30 years in attempting to meet this challenge, the inertial fusion community around the world has invented new technologies in lasers, particle beams, pulse power drivers, diagnostics, target fabrication, and other areas. These technologies have found applications in diverse fields of industry and science. Moreover, simply assembling the teams with the background, experience, and personal drive to meet the challenging requirements of inertial fusion has led to spin-offs in unexpected directions, for example, in laser isotope separation, extreme ultraviolet lithography for microelectronics, compact and inexpensive radars, advanced laser materials processing, and medical technology. The experience of inertial fusion research and development of spinning off technologies has not been unique to any one laboratory or country but has been similar in main research centers in the US, Europe, and Japan. Strengthening and broadening the inertial fusion effort to focus on creating a new source of electrical power (inertial fusion energy [IFE]) that is economically competitive and environmentally benign will yield rich rewards in technology spin-offs. The additional challenges presented by IFE are to make drivers affordable, efficient, and long-lived while operating at a repetition rate of a few Hertz; to make fusion targets that perform consistently at high-fusion yield; and to create target chambers that can repetitively handle greater than 100-MJ yields while producing minimal radioactive by

  2. Academic Training: New Trends in Fusion Research

    CERN Multimedia

    Françoise Benz

    2004-01-01

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

  3. Academic Training: New Trends in Fusion Research

    CERN Multimedia

    Françoise Benz

    2004-01-01

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

  4. Computer applications in controlled fusion research

    International Nuclear Information System (INIS)

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

  5. Microfabricated Ion Beam Drivers for Magnetized Target Fusion

    Science.gov (United States)

    Persaud, Arun; Seidl, Peter; Ji, Qing; Ardanuc, Serhan; Miller, Joseph; Lal, Amit; Schenkel, Thomas

    2015-11-01

    Efficient, low-cost drivers are important for Magnetized Target Fusion (MTF). Ion beams offer a high degree of control to deliver the required mega joules of driver energy for MTF and they can be matched to several types of magnetized fuel targets, including compact toroids and solid targets. We describe an ion beam driver approach based on the MEQALAC concept (Multiple Electrostatic Quadrupole Array Linear Accelerator) with many beamlets in an array of micro-fabricated channels. The channels consist of a lattice of electrostatic quadrupoles (ESQ) for focusing and of radio-frequency (RF) electrodes for ion acceleration. Simulations with particle-in-cell and beam envelope codes predict >10x higher current densities compared to state-of-the-art ion accelerators. This increase results from dividing the total ion beam current up into many beamlets to control space charge forces. Focusing elements can be biased taking advantage of high breakdown electric fields in sub-mm structures formed using MEMS techniques (Micro-Electro-Mechanical Systems). We will present results on ion beam transport and acceleration in MEMS based beamlets. Acknowledgments: This work is supported by the U.S. DOE under Contract No. DE-AC02-05CH11231.

  6. Accelerator ampersand Fusion Research Division 1991 summary of activities

    International Nuclear Information System (INIS)

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations

  7. Accelerator Fusion Research Division 1991 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    Berkner, Klaus H.

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  8. Accelerator & Fusion Research Division 1991 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  9. Beam dynamics studies of the Heavy Ion Fusion Accelerator injector

    International Nuclear Information System (INIS)

    A driver-scale injector for the Heavy Ion Fusion Accelerator project has been built at LBL. This machine has exceeded the design goals of high voltage (> 2 MV), high current (> 0.8 A of K+) and low normalized emittance (< 1 π mm-mr). The injector consists of a 750 keV diode pre-injector followed by an electrostatic quadrupole accelerator (ESQ) which provides strong (alternating gradient) focusing for the space-charge dominated beam and simultaneously accelerates the ions to 2 MeV. The fully 3-D PIC code WARP together with EGUN and POISSON were used to design the machine and analyze measurements of voltage, current and phase space distributions. A comparison between beam dynamics characteristics as measured for the injector and corresponding computer calculations will be presented

  10. Studies on the feasibility of heavy ion beams for inertial confinement fusion

    International Nuclear Information System (INIS)

    This Annual Report summarizes experimental and theoretical investigations carried out in the framework of a feasibility study of inertial confinement fusion by heavy ion beams, funded by the Federal Ministry for Research and Technology. After the completion of the conceptual design study HIBALL with an upgraded version, the investigations concentrated in 1984 mainly on problems of accelerator and target physics. In the area of accelerator physics the main interest was in the production and acceleration of high intensity heavy ion beams of high phase space density and in beam dynamics theory, in the area of target physics on beam-target interaction, radiation hydrodynamics, instabilities and the equation of state of highly compressed hot matter. (orig./AH)

  11. Research and development on vanadium alloys for fusion applications

    Energy Technology Data Exchange (ETDEWEB)

    Zinkle, S.J.; Rowcliffe, A.F. [Oak Ridge National Lab., TN (United States); Matsui, H.; Abe, K. [Tohoku Univ. (Japan); Smith, D.L. [Argonne National Lab., IL (United States); Osch, E. van [NERF, Petten (Netherlands); Kazakov, V.A. [RIAR, Dimitrovgrad (Russian Federation)

    1998-03-01

    The current status of research and development on unirradiated and irradiated V-Cr-Ti alloys intended for fusion reactor structural applications is reviewed, with particular emphasis on the flow and fracture behavior of neutron-irradiated vanadium alloys. Recent progress on fabrication, joining, oxidation behavior, and the development of insulator coatings is also summarized. Fabrication of large (>500 kg) heats of V-4Cr-4Ti with properties similar to previous small laboratory heats has now been demonstrated. Impressive advances in the joining of thick sections of vanadium alloys using GTA and electron beam welds have been achieved in the past two years, although further improvements are still needed.

  12. Accelerator and Fusion Research Division 1989 summary of activities

    International Nuclear Information System (INIS)

    This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations

  13. Accelerator and Fusion Research Division 1989 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1990-06-01

    This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations.

  14. Fusion reactor materials research in China

    International Nuclear Information System (INIS)

    The fusion materials research in China is introduced. Many kinds of structural materials (such as Ti-modified stainless steel, ferritic steel, HT-9, HT-7, oxide dispersion strengthening ferritic steel), tritium breeders (lithium, Li2O, γ-LiAlO2) and plasma facing materials (PFMs) (graphite with TiC and SiC coatings) have been developed or being developed. A systematic research activities on irradiation effects, compatibility, plasma materials interaction, thermal shock during disruption, tritium production, release and permeation, neutron multiplication in Be and Pb, etc. have been performed. The research activities are summarized and some experimental results are also given

  15. Modifications of the laser beam coherence inertial confinement fusion plasmas

    International Nuclear Information System (INIS)

    Inertial confinement fusion by laser requires smoothed laser beam with well-controlled coherence properties. Such beams are made of many randomly distributed intensity maxima: the so-called speckles. As the laser beam propagates through plasma its temporal and spatial coherence can be reduced. This phenomenon is called plasma induced smoothing. For high laser intensities, instabilities developing independently inside the speckles are responsible for the coherence loss. At lower intensities, only collective effects, involving many speckles, can lead to induced smoothing. This thesis is a theoretical, numerical and experimental study of these mechanisms. Accounting for the partially incoherent behavior of the laser beams requires the use of statistical description of the laser-plasma interaction. A model is developed for the multiple scattering of the laser light on the self-induced density perturbations that is responsible for a spreading of the temporal and spatial spectra of the transmitted light. It also serves as a strong seed for the instability of forward stimulated Brillouin scattering that induces both, angular spreading and red-shift of the transmitted light. A statistical model is developed for this instability. A criterion is obtained that gives a laser power (below the critical power for filamentation) above which the instability growth is important. Numerical simulations with the interaction code PARAX and an experiment performed on the ALISE laser facility confirm the importance of these forward scattering mechanisms in the modification of the laser coherence properties. (author)

  16. Particle beam fusion. Progress report, April 1978-December 1978

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    During this period substantial improvements in the theoretical basis for particle beam fusion as well as the execution of critical experiments were instrumental in further definition of the optimum route to our goals of demonstrating scientific and practical feasibility. The major emphasis in the program continues to be focused primarily on issues of power concentration and energy deposition of intense particle beams in solid targets. This utilization of program resources is directed toward conducting significant target implosion and thermonuclear burn experiments using EBFA-I (1 MJ) in the 1981-1983 time period. This step, using EBFA-I, will then set the stage for net energy gain experiments to follow on EBFA-II (> 2 MJ) after 1985. Current program emphasis and activities differ substantially from those stressed in the laser approaches to inertial confinement fusion. Here the critical issues relate to delivering the needed power densities and energies to appropriate targets and to insure that the coupling of energy is efficient and matches target requirements.

  17. Particle beam fusion. Progress report, April 1978-December 1978

    International Nuclear Information System (INIS)

    During this period substantial improvements in the theoretical basis for particle beam fusion as well as the execution of critical experiments were instrumental in further definition of the optimum route to our goals of demonstrating scientific and practical feasibility. The major emphasis in the program continues to be focused primarily on issues of power concentration and energy deposition of intense particle beams in solid targets. This utilization of program resources is directed toward conducting significant target implosion and thermonuclear burn experiments using EBFA-I (1 MJ) in the 1981-1983 time period. This step, using EBFA-I, will then set the stage for net energy gain experiments to follow on EBFA-II (> 2 MJ) after 1985. Current program emphasis and activities differ substantially from those stressed in the laser approaches to inertial confinement fusion. Here the critical issues relate to delivering the needed power densities and energies to appropriate targets and to insure that the coupling of energy is efficient and matches target requirements

  18. New approaches to the economic evaluation of fusion research

    International Nuclear Information System (INIS)

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

  19. Cluster ion beam polishing for inertial confinement fusion target capsules

    International Nuclear Information System (INIS)

    Targets for Inertial Confinement Fusion (ICF) typically consist of a hollow, spherical capsule filled with a mixture of hydrogen isotopes. Typically, these capsules are irradiated by short, intense pulses of either laser light (''direct drive'') or laser-generated. x-rays (''indirect drive''), causing them to implode This compresses and heats the fuel, leading to thermonuclear fusion. This process is highly sensitive to hydrodynamic (e.g., Rayleigh-Taylor) instabilities, which can be initiated by imperfections in the target. Thus, target capsules must be spherical and smooth One of the lead capsule designs for the National Ignition Facility, a 1.8 MJ laser being built at Livermore, calls for a 2-mm- diam capsule with a 150-microm-thick copper-doped beryllium wall. These capsules can be fabricated by sputter depositing the metal onto a spherical plastic mandrel. This results in surfaces with measured Rq's of 50 to 150 nm, as measured with an atomic force microscope For optimal performance the roughness should be below 10 nm rms We have begun studying the use of ion cluster beam polishing as a means of improving the surface finish of as-deposited capsules In this approach, a batch of capsules would be agitated in a bounce pan inside a vacuum chamber during exposure to the cluster beam. This would ensure a uniform beam dose around the capsule. We have performed preliminary experiments on both Be flats and on a stationary Be capsule On the capsule, the measured Rq went from 64 nm before polishing to 15 nm after This result was obtained without any effort at process optimization. Similar smoothing was observed on the planar samples

  20. Heavy Ion Fusion Accelerator Research (HIFAR) year-end report, April 1, 1990--September 30, 1990

    International Nuclear Information System (INIS)

    The basic objective of the Heavy Ion Fusion Accelerator Research (HIFAR) program is to assess the suitability of heavy ion accelerators as igniters for Inertial Confinement Fusion (ICF). A specific accelerator technology, induction acceleration, is being studied at the Lawrence Berkeley Laboratory and at the Lawrence Livermore National Laboratory. The HIFAR program addresses the generation of high-power, high-brightness beams of heavy ions, the understanding of the scaling laws in this novel physics regime, and the validation of new accelerator strategies to cut costs. Key elements to be addressed include: (1) beam quality limits set by transverse and longitudinal beam physics; (2) development of induction accelerating modules, and multiple-beam hardware, at affordable costs; (3) acceleration of multiple beams with current amplification without significant dilution of the optical quality of the beams; (4) final bunching, transport, and accurate focusing on a small target

  1. Heavy Ion Fusion Accelerator Research (HIFAR) year-end report, April 1--September 30, 1988

    International Nuclear Information System (INIS)

    The basic objective of the Heavy Ion Fusion Accelerator Research (HIFAR) program is to assess the suitability of heavy ion accelerators as igniters for Inertial Confinement Fusion (ICF). A specific accelerator technology, the induction linac, has been studied at the Lawrence Berkeley Laboratory and has reached the point at which its viability for ICF applications can be assessed over the next few years. The HIFAR program addresses the generation of high power, high-brightness beams of heavy ions, the understanding of the scaling laws in this novel physics regime, and the validation of new accelerator strategies, to cut costs. Key elements to be addressed include: beam quality limits set by transverse and longitudinal beam physics; development of induction accelerating modules, and multiple-beam hardware, at affordable costs; acceleration of multiple beams with current amplification --both new features in a linac -- without significant dilution of the optical quality of the beams; final bunching, transport, and accurate focusing on a small target

  2. 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

  3. Studies on the feasibility of heavy ion beams for inertial confinement fusion

    International Nuclear Information System (INIS)

    This reports contains some articles contributed to the named conference. These concern the heavy ion fusion program of the Federal Republic of Germany, heavy ion accelerators, the HIBALL projects, storage rings for heavy ion beams, transport of heavy ion beams, and target projects for fusion applications. (HSI)

  4. LLL magnetic fusion research: the first 25 years

    International Nuclear Information System (INIS)

    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

  5. State of controlled nuclear fusion research

    International Nuclear Information System (INIS)

    The development of a commercial fusion reactor requires an adequate solution to the problems of heating and confinement of the nuclear fuel, as well as a considerable effort in materials technology and reactor engineering. A general discussion is presented of the status of the research connected with the most advanced concepts, indicating in each case the present situation and the main problems that must be solved to meet the requeriments estimated for power reactors. In particular, the laser-inertial concept is reviewed in detail. (author)

  6. LIBRA - a light ion beam fusion conceptual reactor design

    International Nuclear Information System (INIS)

    The LIBRA light ion beam fusion commercial reactor study is a self-consistent conceptual design of a 330 MWe power plant with an accompanying economic analysis. Fusion targets are imploded by 4 MJ shaped pulses of 30 MeV Li ions at a rate of 3 Hz. The target gain is 80, leading to a yield of 320 MJ. The high intensity part of the ion pulse is delivered by 16 diodes through 16 separate z-pinch plasma channels formed in 100 torr of helium with trace amounts of lithium. The blanket is an array of porous flexible silicon carbind tubes with Li17Pb83 flowing downward through them. These tubes (INPORT units) shield the target chamber wall from both neutron damage and the shock overpressure of the target explosion. The target chamber is 'self-pumped' by the target explosion generated overpressure into a surge tank partially filled with Li17Pb83 that surrounds the target chamber. This scheme refreshes the chamber at the desired 3 Hz frequently without excessive pumping demands. The blanket multiplication is 1.2 and the tritium breeding ratio is 1.4. The direct capital cost of a 331 MWe LIBRA design is estimated to be 2843 Dollar/kWe while a 1200 MWe LIBRA design will cost approximately 1300 Dollar/kWe. (orig.)

  7. Virtual laboratory for fusion research in Japan

    International Nuclear Information System (INIS)

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

  8. Charge-exchange and fusion reaction measurements during compression experiments with neutral beam heating in the Tokamak Fusion Test Reactor

    International Nuclear Information System (INIS)

    Adiabatic toroidal compression experiments were performed in conjunction with high power neutral beam injection in the Tokamak Fusion Test Reactor (TFTR). Acceleration of beam ions to energies nearly twice the injection energy was measured with a charge-exchange neutral particle analyzer. Measurements were also made of 2.5 MeV neutrons and 15 MeV protons produced in fusion reactions between the deuterium beam ions and the thermal deuterium and 3He ions, respectively. When the plasma was compressed, the d(d,n)3He fusion reaction rate increased a factor of five, and the 3He(d,p)4He rate by a factor of twenty. These data were simulated with a bounce-averaged Fokker-Planck program, which assumed conservation of angular momentum and magnetic moment during compression. The results indicate that the beam ion acceleration was consistent with adiabatic scaling

  9. Customizable scientific web portal for fusion research

    International Nuclear Information System (INIS)

    Web browsers have become a major application interface for participating in scientific experiments such as those in magnetic fusion. The recent advances in web technologies motivated the deployment of interactive web applications with rich features. In the scientific world, web applications have been deployed in portal environments. When used in a scientific research environment, such as fusion experiments, web portals can present diverse sources of information in a unified interface. However, the design and development of a scientific web portal has its own challenges. One such challenge is that a web portal needs to be fast and interactive despite the high volume of information and number of tools it presents. Another challenge is that the visual output of the web portal must not be overwhelming to the end users, despite the high volume of data generated by fusion experiments. Therefore, the applications and information should be customizable depending on the needs of end users. In order to meet these challenges, the design and implementation of a web portal needs to support high interactivity and user customization. A web portal has been designed to support the experimental activities of DIII-D researchers worldwide by providing multiple services, such as real-time experiment status monitoring, diagnostic data access and interactive data visualization. The web portal also supports interactive collaborations by providing a collaborative logbook, shared visualization and online instant messaging services. The portal's design utilizes the multi-tier software architecture and has been implemented utilizing web 2.0 technologies, such as AJAX, Django, and Memcached, to develop a highly interactive and customizable user interface. It offers a customizable interface with personalized page layouts and list of services, which allows users to create a unique, personalized working environment to fit their own needs and interests. This paper describes the software

  10. Studies on the feasibility of heavy ion beams for inertial confinement fusion

    International Nuclear Information System (INIS)

    This Annual Report summarizes the scientific results of work carried out in 1982 in the framework of a feasibility study for inertial confinement fusion with heavy ion beams funded by the German Ministry of Research and Technology. The principal aim of this basic research program is the investigation of key problems and the identification of critical issues of the heavy ion ICF concept in the fields of accelerator research, atomic physics, target physics, and reactor design. The research is carried out by about ten working groups at various research centers and universities. One of the highlights in 1982 was a symposium held end of March at GSI which focussed on a critical analysis of the HIBALL accelerator concept. Whereas technical issues and hardware parameters were found feasible the beam dynamics in the storage rings turned out to be beyond the so far believed stability limits. As a consequence a revised accelerator scenario based on a lower charge state and a higher linac current has been investigated during the last year. First considerations were made on an experimental facility necessary for the study of high-intensity beam dynamics and of beam target interaction. Experimental studies of this kind will be of increasing importance for the future of the project. (orig.)

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

    International Nuclear Information System (INIS)

    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

  12. 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)

  13. Beam non-uniformity smoothing using density valley formed by heavy ion beam deposition in inertial confinement fusion fuel pellet

    International Nuclear Information System (INIS)

    We study the beam nonuniformity smoothing effect of radiation transport in the density valley formed by an ion-beam deposition in a heavy ion-beam inertial confinement fusion pellet by numerical simulations. The simulation results show that the radiation energy is confined in the density valley, and the beam nonuniformity can be smoothed out by the radiation transport along the density valley. In addition, an estimation for the Rayleigh-Taylor instability during the implosion phase is also presented. (author)

  14. Accelerator and Fusion Research Division: 1984 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1985-05-01

    During fiscal 1984, major programmatic activities in AFRD continued in each of five areas: accelerator operations, highlighted by the work of nuclear science users, who produced clear evidence for the formation of compressed nuclear matter during heavy-ion collisions; high-energy physics, increasingly dominated by our participation in the design of the Superconducting Super Collider; heavy-ion fusion accelerator research, which focused on the design of a four-beam experiment as a first step toward assessing the promise of heavy-ion inertial-confinement fusion; and research at the Center for X-Ray Optics, which completed its first year of broadly based activities aimed at the exploitation of x-ray and ultraviolet radiation. At the same time, exploratory studies were under way, aimed at investigating major new programs for the division. During the past year, for example, we took a preliminary look at how we could use the Bevatron as an injector for a pair of colliding-beam rings that might provide the first glimpse of a hitherto unobserved state of matter called the quark-gluon plasma. Together with Livermore scientists, we also conducted pioneering high-gain free-electron laser (FEL) experiments and proposed a new FEL-based scheme (called the two-beam accelerator) for accelerating electrons to very high energies. And we began work on the design of the Coherent XUV Facility (CXF), an advanced electron storage ring for the production of intense coherent radiation from either undulators or free-electron lasers.

  15. Accelerator and Fusion Research Division: 1984 summary of activities

    International Nuclear Information System (INIS)

    During fiscal 1984, major programmatic activities in AFRD continued in each of five areas: accelerator operations, highlighted by the work of nuclear science users, who produced clear evidence for the formation of compressed nuclear matter during heavy-ion collisions; high-energy physics, increasingly dominated by our participation in the design of the Superconducting Super Collider; heavy-ion fusion accelerator research, which focused on the design of a four-beam experiment as a first step toward assessing the promise of heavy-ion inertial-confinement fusion; and research at the Center for X-Ray Optics, which completed its first year of broadly based activities aimed at the exploitation of x-ray and ultraviolet radiation. At the same time, exploratory studies were under way, aimed at investigating major new programs for the division. During the past year, for example, we took a preliminary look at how we could use the Bevatron as an injector for a pair of colliding-beam rings that might provide the first glimpse of a hitherto unobserved state of matter called the quark-gluon plasma. Together with Livermore scientists, we also conducted pioneering high-gain free-electron laser (FEL) experiments and proposed a new FEL-based scheme (called the two-beam accelerator) for accelerating electrons to very high energies. And we began work on the design of the Coherent XUV Facility (CXF), an advanced electron storage ring for the production of intense coherent radiation from either undulators or free-electron lasers

  16. International Fusion Energy Research Centre (IFERC) project

    International Nuclear Information System (INIS)

    The IFERC project is planned to encourage the ITER tokamak project and the fusion demonstration reactor development. In the project, coordination on the design and R and D of the DEMO fusion reactor, fusion reactor simulations and ITER remote experiments are being conducted at JAEA Aomori R and D site. In the present paper, broader approach activities toward realization of fusion power plants such as conceptual design of the DEMO reactor, R and D of fusion materials, testing of fusion reactor components and systems and preparation for the ITER remote experiment are reviewed. (author)

  17. Heavy ion beams for inertial confinement fusion and recent experimental results

    International Nuclear Information System (INIS)

    Methods to confine the fuel during the burn phase, magnetic confinement fusion (MCF), and inertial confinement fusion (ICF), are now believed to be technically feasible. Recent advances in laser fusion, and the progress toward high gain laser fusion considerably raise the probability, that it will be a laser driver to ignite the first high gain fusion pellet under laboratory conditions. The high efficiency (25%) and proven reliability of accelerators, as well as their ability to deliver high intensity beam pulses at a high repetition rate (≥1 Hz) are main assets of ion driven fusion. High energy density in matter induced by heavy ion beams is summarized, followed by an overview of development of plasma lenses for focusing of heavy ion beams and a discussion of energy loss in a dense Z-pinch plasma. (R.P.) 23 refs.; 8 figs

  18. Researches on a reactor core in heavy ion inertial fusion

    CERN Document Server

    Kondo, S; Iinuma, T; Kubo, K; Kato, H; Kawata, S; Ogoyski, A I

    2016-01-01

    In this paper a study on a fusion reactor core is presented in heavy ion inertial fusion (HIF), including the heavy ion beam (HIB) transport in a fusion reactor, a HIB interaction with a background gas, reactor cavity gas dynamics, the reactor gas backflow to the beam lines, and a HIB fusion reactor design. The HIB has remarkable preferable features to release the fusion energy in inertial fusion: in particle accelerators HIBs are generated with a high driver efficiency of ~30-40%, and the HIB ions deposit their energy inside of materials. Therefore, a requirement for the fusion target energy gain is relatively low, that would be ~50 to operate a HIF fusion reactor with a standard energy output of 1GW of electricity. In a fusion reactor the HIB charge neutralization is needed for a ballistic HIB transport. Multiple mechanical shutters would be installed at each HIB port at the reactor wall to stop the blast waves and the chamber gas backflow, so that the accelerator final elements would be protected from the ...

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

    International Nuclear Information System (INIS)

    This report gives a summary of Plasma Fusion Center research activities. Particular emphasis is placed on describing (a) technical progress during the past year, (b) future plans, and (c) research programs and objectives at the individual research group level. In particular, the report covers the following: (1) applied plasma physics, (2) toroidal confinement experiments, (3) mirror confinement experiments, (4) fusion technology and engineering, and (5) fusion systems

  20. Systems approach for condition management design: JET neutral beam system-A fusion case study

    International Nuclear Information System (INIS)

    The maturation of any new technology can be coarsely divided into three stages of a development lifecycle: (1) fundamental research, (2) experimental rig development and testing through to (3) commercialization. With the enhancement of machines like JET, the building of ITER and the initiation of DEMO design activities, the fusion community is moving from stages 1 and 2 towards stage 3. One of the consequences of this transition will be a shift in emphasis from scientific achievement to maximizing machine reliability and availability. The fusion community should therefore be preparing itself for this shift by examining all methods and tools utilized in established engineering sectors that might help to improve these fundamental performance parameters. To this end, the Culham Centre for Fusion Energy (CCFE) has proactively engaged with UK industry to examine whether the development of condition management (CM) systems could help improve such performance parameters. This paper describes an initial CM design case study on the JET neutral beam system. The primary output of this study was the development of a CM design methodology that captures existing experience in fault detection, and classification as well as new methods for fault diagnosis. A summary of the methods used and the potential benefits of data fusion are presented here.

  1. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  2. A 3-year plan for beam science in the heavy-ion fusion virtual national laboratory

    International Nuclear Information System (INIS)

    In December 1998, LBNL Director Charles Shank and LLNL Director Bruce Tarter signed a Memorandum of Agreement to create the Heavy-Ion Fusion Virtual National Laboratory (HIF-VNL) with the purpose of improving the efficiency and productivity of heavy ion research through coordination of the two laboratories' efforts under one technical director. In 1999, PPPL Director Robert Goldston signed the VNL MOA for PPPL's heavy-ion fusion group to join the VNL. LBNL and LLNL each contribute about 45% of the $10.6 M/yr trilab VNL effort, and PPPL contributes currently about 10% of the VNL effort. The three labs carry out collaborative experiments, theory and simulations of a variety of intense beam scientific issues described below. The tri-lab HIF VNL program is part of the DOE Office of Fusion Energy Sciences (OFES) fusion program. A short description of the four major tasks areas of HIF-VNL research is given in the next section. The task areas are: High Current Experiment, Final Focus/Chamber Transport, Source/Injector/Low Energy Beam Transport (LEBT), and Theory/Simulation. As a result of the internal review, more detailed reviews of the designs, costs and schedules for some of the tasks have been completed, which will provide more precision in the scheduled completion dates of tasks. The process for the ongoing engineering reviews and governance for the future management of tasks is described in section 3. A description of the major milestones and scientific deliverables for flat guidance budgets are given in section 4. Section 5 describes needs for enabling technology development for future experiments that require incremental funding

  3. Great expectations: a review of nuclear fusion research

    International Nuclear Information System (INIS)

    Fusion research policy has recently come under scrutiny, prompted by rising research costs and increasing doubt about the value of such long-term work. This paper reviews the basic principles of fusion, the research and development still required, the costs of research to date, justifications for it, and future policy options; and examines in broad terms some of the ways in which fusion can be and has been evaluated. Throughout, the emphasis is on the need to compare fusion on equal terms with those technological options with which it may compete, and in the context of different energy futures. (author)

  4. European fusion energy research and international ITER project

    International Nuclear Information System (INIS)

    The scientific feasibility of fusion energy has been demonstrated in recent tokamak experiments in Europe, Japan and the United States. The basic features of the confinement of high temperature hydrogen plasmas by strong magnetic fields are reasonably well understood, which creates a high level of confidence in the performance of the next step fusion devices. The most powerful fusion device in the world is the Joint European Torus (JET), which has ensured the European Fusion Programme its leading position in international fusion research. The nest step fusion reactor, ITER (International Thermonuclear Experimental Reactor), is an international project involving the cooperation of the European Union, Japan, The Russian Federation and USA. The overall objective of ITER is to demonstrate the scientific and technological feasibility of fusion power for peaceful purposes. Membership in the European Union would automatically make Finland a participant in the Community Fusion Programme and the international ITER project. (orig.)

  5. The Role of the JET Project in Global Fusion Research

    DEFF Research Database (Denmark)

    Jensen, Vagn Orla

    1983-01-01

    The aim of nuclear fusion research is to make fusion energy available as a new energy source. Fusion processes occur naturally in the sun, where hydrogen nuclei release energy by combining to form helium. A fusion reactor on earth will require even higher temperatures than in the interior...... of the sun, and it will be based on deuterium and tritium reactions. JET (Joint European Torus) is a major fusion experiment now under construction near Abingdon in the UK It is aimed at producing conditions approximating those necessary in a fusion reactor. The results expected from JET should permit...... a realistic evaluation of the prospects for fusion power and serve as a basis for the design of the next major fusion experiment....

  6. Independent experts give strong backing to Euro fusion research

    International Nuclear Information System (INIS)

    An independent scientific team has spent 1990 reviewing Europe's fusion research programme for the European Communities Commission. The 1990 evaluation board headed by Prof. U. Colombo, ENEA chairman, Italy's energy research commission, recommends 'maintaining fusion as a priority in the Community's energy research strategy'

  7. Beyond ITER: neutral beams for a demonstration fusion reactor (DEMO) (invited).

    Science.gov (United States)

    McAdams, R

    2014-02-01

    In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed. PMID:24593596

  8. Progress of inertial confinement fusion (ICF) research

    International Nuclear Information System (INIS)

    In this article, we briefly describe the recent progress of ICF research. Four topics in this field are selected which are considered as the most important at present. These are the 'Cannonball' target; high power krypton fluoride (KrF) laser; Ion beam diodes and imploding foil/plasma. About the 'Cannonball' target, its principle and its advantages over the ordinary ablation drive are given. It is particularly indicated that by using this type of target, the Japanese researchers have gotten, thus far, the highest yield of neutrons in the world, i. e. 4 x 1010 neutrons per pulse. The important problem of hole sealing of such target is also discussed. The second topic described above is the powerful KrF excimer laser pumped by electron beams. This laser is now generally regarded as one of more promising lasers as a driver for ICF. Here we briefly describe the complex kinetics of pumping, quenching, radiation and absorption of this very interesting laser. A compression of KrF laser pulse length from about 100 nanosecond (ns) to a few ns is necessary for ICF work. We describe three of the compression methods, namely: pulse spletting and then stacking; Raman back scattering and the mixing of these two. In the third topic it is discussed on the present status of ion beam production, especially on the diodes which produce the ion beams. Three kinds of the diodes are mentioned. These are pinched reflex diode (PRD), diode with externally applied magnetic field and hybrid amphion diode. New works of Reiden-IV, in Institute of Laser Engineering, Osaka and Etigol in Nagaoka Technical University, Nagaoka are also reported. The 4th topic concerned is the imploding foil/plasma. This method can produce plasma of very high temperature and very intensive soft X-ray which may either be used to produce X-ray laser or used as a new driver for ICF

  9. Software problems in magnetic fusion research

    International Nuclear Information System (INIS)

    The main world effort in magnetic fusion research involves studying the plasma in a Tokamak device. Four large Tokamaks are under construction (TFTR in USA, JET in Europe, T15 in USSR and JT60 in Japan). To understand the physical phenomena that occur in these costly devices, it is generally necessary to carry out extensive numerical calculations. These computer simulations make use of sophisticated numerical methods and demand high power computers. As a consequence they represent a substantial investment. To reduce software costs, the computer codes are more and more often exhanged among scientists. Standardization (STANDARD FORTRAN, OLYMPUS system) and good documentation (CPC program library) are proposed to make codes exportable. Centralized computing centers would also help in the exchange of codes and ease communication between the staff at different laboratories. (orig.)

  10. Major achievements and challenges of fusion research

    Science.gov (United States)

    Tendler, Michael

    2015-09-01

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

  11. The role of innovations in fusion research. Artsimovich memorial lecture

    International Nuclear Information System (INIS)

    The IAEA Conference on Plasma Physics and Controlled Nuclear Fusion Research traditionally is opened with the Artsimovich Memorial Lecture, this time given by Academician Ryutov. Using some examples from the field of fusion he illustrates the role of subsequent technological developments on the bringing to fruition of creative ideas in physics. The desirability to find forms of organization within the fusion research program that would allow the continued exploration of non-conventional ideas and alternative concepts is advocated

  12. Accelerator and Fusion Research Division: Summary of activities, 1986

    Energy Technology Data Exchange (ETDEWEB)

    1987-04-15

    This report contains a summary of activities at the Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division for the year 1986. Topics and facilities investigated in individual papers are: 1-2 GeV Synchrotron Radiation Source, the Center for X-Ray Optics, Accelerator Operations, High-Energy Physics Technology, Heavy-Ion Fusion Accelerator Research and Magnetic Fusion Energy. Six individual papers have been indexed separately. (LSP)

  13. Accelerator and Fusion Research Division: Summary of activities, 1986

    International Nuclear Information System (INIS)

    This report contains a summary of activities at the Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division for the year 1986. Topics and facilities investigated in individual papers are: 1-2 GeV Synchrotron Radiation Source, the Center for X-Ray Optics, Accelerator Operations, High-Energy Physics Technology, Heavy-Ion Fusion Accelerator Research and Magnetic Fusion Energy. Six individual papers have been indexed separately

  14. Fusion Energy and Stopping Power in a Degenerate DT Pellet Driven by a Laser-Accelerated Proton Beam

    Science.gov (United States)

    Mehrangiz, M.; Ghasemizad, A.; Jafari, S.; Khanbabaei, B.

    2016-06-01

    In this paper, we have improved the fast ignition scheme in order to have more authority needed for high-energy-gain. Due to the more penetrability and energy deposition of the particle beams in fusion targets, we employ a laser-to-ion converter foil as a scheme for generating energetic ion beams to ignite the fusion fuel. We find the favorable intensity and wavelength of incident laser by evaluating the laser-proton conversion gain. By calculating the source-target distance, proton beam power and energy are estimated. Our analysis is generalized to the plasma degeneracy effects which can increase the fusion gain several orders of magnitude by decreasing the ion-electron collisions in the plasma. It is found that the wavelength of 0.53 μm and the intensity of about 1020 W/cm2, by saving about 10% conversion coefficient, are the suitable measured values for converting a laser into protons. Besides, stopping power and fusion burn calculations have been done in degenerate and non-degenerate plasma mediums. The results indicate that in the presence of degeneracy, the rate of fusion enhances. Supported by the Research Council of University of Guilan

  15. Inertial confinement fusion driven by heavy ion beams

    International Nuclear Information System (INIS)

    Heavy ion inertial confinement fusion is reviewed with emphasis on the physics of fusion targets for direct and indirect drive, on radio-frequency and induction linear accelerators as the major options for reactor drivers, and on accelerator and plasma target experiments for heavy ion fusion, now starting at the SIS/ESR accelerator in Darmstadt. (author)

  16. Nuclear Fusion - Open Questions For Research

    International Nuclear Information System (INIS)

    Nuclear fusion, as one of the main energy source for the 21 century, is still in the stage of extensive scientific research which is aimed toward achieving thermonuclear ignition. In the present talk I will shortly review the status of the main approaches to achieve net thermonuclear fusion energy and will mainly describe the achievements and open questions of the Inertial Confinement Fusion method, where intense lasers are used to compress and heat a small pellet of DT up to ignition and burn conditions. It is well recognized that the main obstacle to achieve ignition in the ICF approach is the development of hydrodynamic instabilities on both sides of the compressed shell that may cause shell breakup and ignition failure. In the present work, we review our recent theoretical, numerical and experimental work that contribute to a better understanding the evolution of instabilities at the various stages of the pellet implosion. The perturbations, from which the instabilities grow, are seeded by both surface roughness and laser intensity non-uniformity. In order to study the laser imprint process we have carried out numerical simulations and modeling in order to get the equivalent mass perturbation in the target as a function of perturbation wavelength, laser intensity and pulse shape and laser smoothing technique. Using the initial mass perturbation spectrum we estimating what is the required initial perturbation amplitude (from both surface roughness and laser imprint) that will not cause shell breakup. Until recently, most of the simulations and models developed to describe the evolution of the instability were done in two-dimensions(2D). We have recently performed full numerical simulations and extended our models to describe the evolution of three-dimensional(3D) perturbations. It was found that there are differences between the evolution of the instability in 2D and 30, which is caused by the differences in the kinematic drag force that is decelerating the

  17. Research in Inertial Fusion Sciences: Now and in the Future

    International Nuclear Information System (INIS)

    We review the current and future state of research in inertial fusion sciences. We describe the National Ignition Facility (NIF), the IFE development plan, applications of inertial confinement fusion (ICF) to various high-energy sciences, uses of petawatt laser systems, and concepts for the ICF integrated research experiment (IRE) and IFE power plants

  18. Developing models for simulation of pinched-beam dynamics in heavy ion fusion. Revision 1

    International Nuclear Information System (INIS)

    For heavy-ion fusion energy applications, Mark and Yu have derived hydrodynamic models for numerical simulation of energetic pinched-beams including self-pinches and external-current pinches. These pinched-beams are applicable to beam propagation in fusion chambers and to the US High Temperature Experiment. The closure of the Mark-Yu model is obtained with adiabatic assumptions mathematically analogous to those of Chew, Goldberger, and Low for MHD. Features of this hydrodynamic beam model are compared with a kinetic treatment

  19. Synthesis of transactinide nuclei in cold fusion reactions using radioative beams

    OpenAIRE

    Smolanczuk, Robert

    2009-01-01

    Chances of synthesis of transactinide nuclei in cold fusion reactions (one-neutron-out) reactions using radioactive beams are evaluated. Because intensities of radioactive beams are in most of the cases significantly lower than the ones of the stable beams, reactions with the highest radioactive beam intensities for the particular elements are considered. The results are compared with the recent ones obtained by Loveland who investigated the same nuclei.

  20. Proton Beam Fast Ignition Fusion: Nonlinear Generation of Bθ-Fields by Knock-on Electrons

    Science.gov (United States)

    Stefan, V. Alexander

    2011-10-01

    The knock-on electrons, generated by the fast proton beam in interaction with the free and bound electrons in a precompressed DT fusion pellet, outrun the proton beam, generating the Bθ-fields ahead of the beam, which may lead to the defocusing of the beam, if Bθ Tabak et al, Phys. Plasmas 1 (5), 1626 (1994); H. L. Buchanan, F. W. Chambers, E. P. Lee, S. S. Yu, R. J. Briggs, and M. N. Rosenbluth, LLNL, UCRL Report 82586, 1979.

  1. Nuclear Fusion Research Understanding Plasma-Surface Interactions

    CERN Document Server

    Clark, Robert E.H

    2005-01-01

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

  2. Studies on the feasibility of heavy-ion beams for inertial confinement fusion

    International Nuclear Information System (INIS)

    This annual report summarizes the scientific results of work carried out in 1981 in the framework of a feasibility study for inertial confinement fusion (ICF) with heavy ion beams. This program, established in autumn 1979 and funded by the German Ministry for Science and Technology, is devoted in a first period until 1984 to the study of fundamental aspects of the field. Its principal aims are the investigation of key problems and the identification of critical issues of the heavy ion ICF concept in the fields of accelerator research, pellet physics, atomic physics, and reactor design. The research is carried out by about ten working groups at various German research centers and universities. In addition, together with a group of the University of Wisconsin a conceptual design study for a reactor plant (HIBALL) has been started in 1980 and was continued 1981. (orig.)

  3. Basics of Fusion-Fission Research Facility (FFRF) as a Fusion Neutron Source

    International Nuclear Information System (INIS)

    FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device (1). FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.

  4. Basics of Fusion-Fissison Research Facility (FFRF) as a Fusion Neutron Source

    Energy Technology Data Exchange (ETDEWEB)

    Leonid E. Zakharov

    2011-06-03

    FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device [1]. FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.

  5. Socio-Economic research on fusion SERF 3(2001-2003) External Costs of Fusion

    International Nuclear Information System (INIS)

    Based on SEAFP project (Raeder et al, 1995) findings a preliminary assessment of environmental external costs associated to fusion power was performed under the framework of the first phase of the SERF (Socioeconomic Research on Fusion) project (Saez et al, 1999). This study showed very low external costs of fusion power compared with other traditional and new energy generating technologies. In order to update the assessment of externalities of fusion power, SERF2 project a new plant was included and an analysis of the key variables influencing the external cost was carried out. In the new phase of the SERF project, SERF3, three new additional plant models have been introduced with the aim of assessing the possibilities of silicon carbide to be used as structural material for fusion power plants. Furthermore, comparison of fusion external costs with those of other generation technologies in the state of technology development expected for 2050 has been also performed. (Author)

  6. Analysis of fusion neutron production in EAST with neutral beam injection

    International Nuclear Information System (INIS)

    Background: The neutron emission rate increases rapidly with high-power deuterium beam injected into deuterium plasmas. It is necessary to calculate the neutron production in Experimental Advanced Superconducting Tokamak (EAST) for the radiation safety. Purpose: We aim to provide reference for developing new detection systems of fusion neutron and neutron radiation shielding design. Methods: Neutron emission rate was calculated using the typical particle model and analysis method. The relationships were analyzed among the fusion neutron production and the ion density, ion temperature, neutral beam energy and neutral beam power respectively. Results: The results demonstrated that the total fusion neutron production was 1016 n·s-1 with 80-keV, 4-MW neutral beam injection. Conclusion: Neutron intensity in EAST will increase by a factor of ten when appropriate neutral beam injection is applied. It can be referred for further performance improvement and radiation protection of EAST. (authors)

  7. Focused neutral beams with low chaotic divergence for plasma heating and diagnostics in magnetic fusion devices

    International Nuclear Information System (INIS)

    A series of neutral beam injectors has been developed in the Budker Institute of Nuclear Physics for plasma heating and diagnostics in modern fusion devices. Ion optical system of these injectors is optimized to produce ion beams with low angular divergence. In order to provide beam focusing, the grids are formed to be spherical segments. Such geometrically focused neutral beams are particularly advantageous for plasma diagnostics when high spatial resolution is required. Another application of these beams is plasma heating in the machines with narrow ports through which only small size, high power density beams can be transported. (author)

  8. NSPEC - A neutron spectrum code for beam-heated fusion plasmas

    International Nuclear Information System (INIS)

    A 3-dimensional computer code is described, which computes neutron spectra due to beam heating of fusion plasmas. Three types of interactions are considered; thermonuclear of plasma-plasma, beam-plasma and beam-beam interactions. Beam deposition is modelled by the NFREYA code. The applied steady state beam distribution as a function of pitch angle and velocity contains the effects of energy diffusion, friction, angular scattering, charge exchange, electric field and source pitch angle distribution. The neutron spectra, generated by Monte-Carlo methods, are computed with respect to given lines of sight. This enables the code to be used for neutron diagnostics. (author)

  9. Experiences with remote collaborations in fusion research

    International Nuclear Information System (INIS)

    The magnetic fusion research community has considerable experience in placing remote collaboration tools in the hands of real user. The ability to remotely view operations and to control selected instrumentation and analysis tasks has been demonstrated. University of Wisconsin scientists making turbulence measurements on TFTR: (1) were provided with a remote control room from which they could operate their diagnostic, while keeping in close contact with their colleagues in Princeton. LLNL has assembled a remote control room in Livermore in support of a large, long term collaboration on the DIII-D tokamak in San Diego. (2) From the same control room, a joint team of MIT and LLNL scientists has conducted full functional operation of the Alcator C-Mod tokamak located 3,000 miles away in Cambridge Massachusetts. (3) These early efforts have been highly successful, but are only the first steps needed to demonstrate the technical feasibility of a complete facilities on line environment. These efforts have provided a proof of principle for the collaboratory concept and they have also pointed out shortcomings in current generation tools and approaches. Current experiences and future directions will be discussed

  10. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    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

  11. Induction-accelerator heavy-ion fusion: Status and beam physics issues

    International Nuclear Information System (INIS)

    Inertial confinement fusion driven by beams of heavy ions is an attractive route to controlled fusion. In the U.S., induction accelerators are being developed as open-quotes driversclose quotes for this process. This paper is divided into two main sections. In the first section, the concept of induction-accelerator driven heavy-ion fusion is briefly reviewed, and the U.S. program of experiments and theoretical investigations is described. In the second, a open-quotes taxonomyclose quotes of space-charge-dominated beam physics issues is presented, accompanied by a brief discussion of each area

  12. International information exchange in fusion research

    International Nuclear Information System (INIS)

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

  13. Heavy ion beam transport and focusing with an insulator guide in inertial confinement fusion

    International Nuclear Information System (INIS)

    One of the key issues on the heavy ion beam inertial confinement fusion is an efficient transport and beam focusing. To get a fine focusing on the fuel pellet, neutralization of the space change of an incident beam is required. The space charge of beam has to be neutralized for the fine focusing. In this paper, we propose to employ an insulator tube guide, through which a heavy ion beam is transported and focused. We confirm that the beam space charge is effectively neutralized by electrons emitted from the insulator beam guide and the ion beam fine focusing is realized. This result shows a possibility of a good beam focusing by the insulator beam guide. (author)

  14. Pathways to Energy from Inertial Fusion. An Integrated Approach. Report of a Coordinated Research Project 2006-2010

    International Nuclear Information System (INIS)

    The IAEA has continuously demonstrated its commitment to supporting the development of safe and environmentally clean nuclear fusion energy. Statistics show that at the current rate of energy consumption, fusion energy would remain an inexhaustible energy source for humankind for millions of years. Furthermore, some of the existing and foreseen risks - such as nuclear waste disposal and rising greenhouse gas emissions from the use of fossil fuels - can also be reduced. In the quest for fusion energy, two main lines of research and development are currently being pursued worldwide, namely the inertial and the magnetic confinement fusion concepts. For both approaches, the IAEA has conducted coordinated research activities focusing on specific physics and technological issues relevant the establishment of the knowledge base and foundation for the design and construction of fusion power plants. This report describes the recent research and technological developments and challenges in inertial fusion energy within the framework of such a coordinated research effort. The coordinated research project on Pathways to Energy from Inertial Fusion: An Integrated Approach was initiated in 2006 and concluded in 2010. The project involved experts and institutions from 16 Member States, addressing issues relevant to advancing inertial fusion energy research and development in its practical applications. The key topics addressed include: (i) high repetition rate, low cost, high efficiency ignition drivers; (ii) beam-matter/beam-plasma interaction related to inertial fusion target physics; (iii) target fusion chamber coupling and interface; and (iv) integrated inertial fusion power plant design. Participants in this coordinated research project have contributed 17 detailed research and technology progress reports of work performed at national and international levels. This report compiles all these reports while highlighting the various achievements.

  15. Parasitic components from charge transfer in neutral beams for fusion

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, O.A.

    1978-02-01

    Charge exchange within accelerating grids in neutral beam systems produces parasitic beam components which degrade the performance of the systems. These components also change the plasma confinement properties at the target. This note discusses parasitic beams produced in three types of grid systems: (1) TFTR/MFTF sources, (2) accel-decel grids for low energy beams, and (3) the JSC negative ion system.

  16. Effects of sawtooth crashes on beam ions and fusion product tritons in JET

    Energy Technology Data Exchange (ETDEWEB)

    Marcus, F.B.; Hone, M.A.; Jarvis, O.N.; Loughlin, M.J.; Sadler, G. [Commission of the European Communities, Abingdon (United Kingdom). JET Joint Undertaking; Adams, J.M.; Bond, D.S.; Watkins, N. [UKAEA Harwell Lab. (United Kingdom). Energy Technology Div.; Howarth, P.J.A. [Birmingham Univ. (United Kingdom)

    1994-07-01

    The effect of a sawtooth crash on the radial distribution of the slowing down fusion product tritons and on beams ions, is examined with measurements of the 2.5 MeV and 14 MeV neutron emission line-integrals before and after sawtooth crashes. In deuterium discharges, the 14 MeV neutron production was wholly attributable to burnup of the 1 MeV fusion product tritons from d-d fusion. The local emissivity of 14 MeV neutrons, and hence of the profile of thermalizing tritons, is shown to be only weakly affected by crashes in the discharges studied. This is in contradiction with the apparent behaviour of injected beam ions as deduced from a study of the considerable changes in local emissivity of the 2.5 MeV neutrons. Nevertheless, the behaviour of the fusion product tritons is consistent with the scaling of the beam injected deuterium. 1 ref., 6 figs.

  17. Progress in inertial confinement fusion with light ion beams at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Light ion beams offer the possibility of a very efficient and low-cost driver for Inertial Confinement Fusion (ICF). The energy deposition is straightforward since the ions deposit their energy in a dense plasma that prevents microscopic instabilities from producing preheating electrons. The difficulty with light ions has been the focusability. In 1984, a proof-of-principle experiment on Proto I, at the same current density and charge density required for inertial fusion on the Particle Beam Fusion Accelerator II (PBFA II), showed that intense ion beams can be focused to the required divergence with the correct local physics. In 1985, diode and accelerator technology was examined on PBFA I at the same current and diode radius required for fusion on PBFA II. PBFA II finished its construction phase with a successful first shot on December 11, 1985. The accelerator is now being characterized and brought to full operational status

  18. Research on information fusion for engineering system integrated health management

    Science.gov (United States)

    Gao, Zhanbao; Li, Xingshan; Sun, Cong; Liu, Qi

    2006-11-01

    Integrated Health Management technology is the emerging paradigm in system supervision and maintenance area, and it is the key to achieving true condition-based maintenance. But this task is complicated by the extremely large amount of the data available, the existence of uncertainties, and interactive engineering system operational conditions. Therefore, it is reasonable to research the health information fusion technology to achieve better performance and a higher level of autonomy for IHM system. This paper analyses the requirements of the information fusion in an IHM system, describes the fusion application areas, proposes the Health Sensing Unit (HSU) concept, and designs the distributed hierarchical fusion architecture. Using the confidence distance matrix as the measure of HSU's performance, this paper proposes a fusion algorithm to fuse multiple HSUs' output, and figure out the system health index according to the maximum likelihood principle. The simulation result yields conclusive evidence that fusion can be very valuable in the IHM technology for the system supervision and maintenance.

  19. Plasma physics and controlled fusion research during half a century

    International Nuclear Information System (INIS)

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

  20. Plasma physics and controlled fusion research during half a century

    Energy Technology Data Exchange (ETDEWEB)

    Lehnert, Bo

    2001-06-01

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

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

    International Nuclear Information System (INIS)

    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

  2. Customizable Scientific Web Portal for Fusion Research

    International Nuclear Information System (INIS)

    The Web browser has become one of the major application interfaces for remotely participating in magnetic fusion experiments. Recently in other areas, web portals have begun to be deployed. These portals are used to present very diverse sources of information in a unified way. While a web portal has several benefits over other software interfaces, such as providing single point of access for multiple computational services, and eliminating the need for client software installation, the design and development of a web portal has unique challenges. One of the challenges is that a web portal needs to be fast and interactive despite a high volume of tools and information that it presents. Another challenge is the visual output on the web portal often is overwhelming due to the high volume of data generated by complex scientific instruments and experiments; therefore the applications and information should be customizable depending on the needs of users. An appropriate software architecture and web technologies can meet these problems. A web-portal has been designed to support the experimental activities of DIII-D researchers worldwide. It utilizes a multi-tier software architecture, and web 2.0 technologies, such as AJAX, Django, and Memcached, to develop a highly interactive and customizable user interface. It offers a customizable interface with personalized page layouts and list of services for users to select. The users can create a unique personalized working environment to fit their own needs and interests. Customizable services are: real-time experiment status monitoring, diagnostic data access, interactive data visualization. The web-portal also supports interactive collaborations by providing collaborative logbook, shared visualization and online instant message services. Furthermore, the web portal will provide a mechanism to allow users to create their own applications on the web portal as well as bridging capabilities to external applications such as

  3. Customisable Scientific Web Portal for Fusion Research

    International Nuclear Information System (INIS)

    The Web browser has become one of the major application interfaces for remotely participating in magnetic fusion. Web portals are used to present very diverse sources of information in a unified way. While a web portal has several benefits over other software interfaces, such as providing single point of access for multiple computational services, and eliminating the need for client software installation, the design and development of a web portal has unique challenges. One of the challenges is that a web portal needs to be fast and interactive despite a high volume of tools and information that it presents. Another challenge is the visual output on the web portal often is overwhelming due to the high volume of data generated by complex scientific instruments and experiments; therefore the applications and information should be customizable depending on the needs of users. An appropriate software architecture and web technologies can meet these problems. A web-portal has been designed to support the experimental activities of DIII-D researchers worldwide. It utilizes a multi-tier software architecture, and web 2.0 technologies, such as AJAX, Django, and Memcached, to develop a highly interactive and customizable user interface. It offers a customizable interface with personalized page layouts and list of services for users to select. Customizable services are: real-time experiment status monitoring, diagnostic data access, interactive data visualization. The web-portal also supports interactive collaborations by providing collaborative logbook, shared visualization and online instant message services. Furthermore, the web portal will provide a mechanism to allow users to create their own applications on the web portal as well as bridging capabilities to external applications such as Twitter and other social networks. In this series of slides, we describe the software architecture of this scientific web portal and our experiences in utilizing web 2.0 technologies. A

  4. Romanian research in the field of Tokamak fusion reactors

    International Nuclear Information System (INIS)

    To re-create the conditions of the sun and stars for the production of fusion energy on earth, scientists most accomplish three major tasks. They have already passed the first task by achieving the necessary temperatures. In same cases, they have attained temperatures as high as 510 million degrees, 20 times more then the temperature at the center of the sun. Secondly, they need to demonstrate sustained reactions where substantial amounts of energy are produced. The third major milestone for fusion would be operation of a demonstration fusion power plant. Many different magnetic confined schemes have been studied. The one which is receiving the greatest attention in the international magnetic fusion energy programme is the tokamak concept, and represents actually the most advanced fusion devices. The advantage of fusion are: - abundant fuel supply; - no risk of a nuclear accident; - no air pollution; - no high-level nuclear waste; - no generation of weapons material. The present objectives and research priorities of the fusion community are: - continuation of ongoing research; - concept improvements; - long term technology. Our research programme in the field of tokamak fusion reactions is performed mainly in the frame of international cooperation with 'I.V. Kurchatov' Nuclear Fusion Institute from Moscow, Institute of Applied Mathematics from Grenoble, Research Center from Cadarache, 'Max-Planck' Institute for Plasma Physics from Garching at Munich and Columbia University from New York. The activities carried out under our programme are closely coordinated with those of the European Atomic Energy Community and are related to current problems concerning equilibrium, stability, transport and diagnostics of tokamak plasmas. Our results are mentioned in the International Atomic Energy Agency's World Survey of Activities in Controlled Fusion Research in 1997 and the European Community's Reports EUR FUR BRU from 1993 and 1996. (author)

  5. Finnish Fusion Research Programme Yearbook 1993-1994

    International Nuclear Information System (INIS)

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

  6. Several atomic-physics issues connected with the use of neutral beams in fusion experiments

    International Nuclear Information System (INIS)

    Energetic neutral beams are used for heating and diagnostics in present magnetic fusion experiments. They are also being considered for use in future large experiments. Atomic physics issues are important for both the production of the neutral beams and the interaction of the beams and the plasma. Interest in neutral beams based on negative hydrogen ions is growing, largely based on advances in producing high current ion sources. An extension of the negative ion approach has been the suggestion to use negative ions of Z > 1 elements, such as carbon and oxygen, to form high power neutral beams for plasma heating

  7. Multiple-beam laser–plasma interactions in inertial confinement fusion

    International Nuclear Information System (INIS)

    The experimental evidence for multiple-beam laser-plasma instabilities of relevance to laser driven inertial confinement fusion at the ignition scale is reviewed, in both the indirect and direct-drive approaches. The instabilities described are cross-beam energy transfer (in both indirectly driven targets on the NIF and in direct-drive targets), multiple-beam stimulated Raman scattering (for indirect-drive), and multiple-beam two-plasmon decay instability (in direct drive). Advances in theoretical understanding and in the numerical modeling of these multiple beam instabilities are presented

  8. Heavy-ion fusion driver research at Berkeley and Livermore

    International Nuclear Information System (INIS)

    The Department of Energy is restructuring the U.S. fusion program to place a greater emphasis on science. As a result, we will not build the ILSE or Elise heavy ion fusion (HIF) facilities described in 1992 and 1994 conferences. Instead we are performing smaller experiments to address important scientific questions. Accelerator technology for HIF is similar to that for other applications such as high energy physics and nuclear physics. The beam physics, however, differs from the physics encountered in most accelerators, where the pressure arising from the beam temperature (emittance) is the dominant factor determining beam size and focusing system design. In HIF, space charge is the dominant feature, leading us into a parameter regime where.the beam plasma frequency becomes comparable to the betatron frequency. Our experiments address the physics of non-neutral plasmas in this novel regime. Because the beam plasma frequency is low, Particle-in-cell (PIC) simulations provide a good description of most of our experiments. Accelerators for HIF consist of several subsystems: ion sources, injectors, matching sections, combiners, acceleration sections with electric and magnetic focusing, beam compression and bending sections, and a system to focus the beams onto the target. We are currently assembling or performing experiments to address the physics of all these subsystems. This paper will discuss experiments in injection, combining, and bending

  9. Accelerator and Fusion Research Division annual report, October 1981-September 1982. Fiscal year 1982

    International Nuclear Information System (INIS)

    This report covers the activities of LBL's Accelerator and Fusion Research Division (AFRD) during 1982. In nuclear physics, the Uranium Beams Improvement Project was concluded early in the year, and experimentation to exploit the new capabilities began in earnest. Technical improvement of the Bevalac during the year centered on a heavy-ion radiofrequency quadrupole (RFQ) as part of the local injector upgrade, and we collaborated in studies of high-energy heavy-ion collision facilities. The Division continued its collaboration with Fermilab to design a beam-cooling system for the Tevatron I proton-antiprotron collider and to engineer the needed cooling components for the antiproton. The high-field magnet program set yet another record for field strength in an accelerator-type dipole magnet (9.2 T at 1.8 K). The Division developed the design for the Advanced Light Source (ALS), a 1.3-GeV electron storage ring designed explicitly (with low beam emittance and 12 long straight sections) to generate high-brilliance synchrotron light from insertion devices. The Division's Magnetic Fusion Energy group continued to support major experiments at the Princeton Plasma Physics Laboratory, the Lawrence Livermore National Laboratory (LLNL), and General Atomic Co. by developing positive-ion-based neutral-beam injectors. Progress was made toward converting our major source-test facility into a long-pulse national facility, the Neutral Beam Engineering Test Facility, which was completed on schedule and within budget in 1983. Heavy Ion Fusion research focused on planning, theoretical studies, and beam-transport experiments leading toward a High Temperature Experiment - a major test of this promising backup approach to fusion energy

  10. Accelerator and Fusion Research Division annual report, October 1981-September 1982. Fiscal year 1982

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, R.K.; Bouret, C. (eds.)

    1983-05-01

    This report covers the activities of LBL's Accelerator and Fusion Research Division (AFRD) during 1982. In nuclear physics, the Uranium Beams Improvement Project was concluded early in the year, and experimentation to exploit the new capabilities began in earnest. Technical improvement of the Bevalac during the year centered on a heavy-ion radiofrequency quadrupole (RFQ) as part of the local injector upgrade, and we collaborated in studies of high-energy heavy-ion collision facilities. The Division continued its collaboration with Fermilab to design a beam-cooling system for the Tevatron I proton-antiprotron collider and to engineer the needed cooling components for the antiproton. The high-field magnet program set yet another record for field strength in an accelerator-type dipole magnet (9.2 T at 1.8 K). The Division developed the design for the Advanced Light Source (ALS), a 1.3-GeV electron storage ring designed explicitly (with low beam emittance and 12 long straight sections) to generate high-brilliance synchrotron light from insertion devices. The Division's Magnetic Fusion Energy group continued to support major experiments at the Princeton Plasma Physics Laboratory, the Lawrence Livermore National Laboratory (LLNL), and General Atomic Co. by developing positive-ion-based neutral-beam injectors. Progress was made toward converting our major source-test facility into a long-pulse national facility, the Neutral Beam Engineering Test Facility, which was completed on schedule and within budget in 1983. Heavy Ion Fusion research focused on planning, theoretical studies, and beam-transport experiments leading toward a High Temperature Experiment - a major test of this promising backup approach to fusion energy.

  11. Spherical tokamak research for fusion reactor

    International Nuclear Information System (INIS)

    Between ITER and the commercial fusion reactor, there are many technological problems to be solved such as cost, neutron and steady-state operation. In the conceptual design of VECTOR and Slim CS reactors it was shown that the key is 'low aspect ratio'. The spherical tokamak (ST) has been expected as the base for fusion reactors. In US, ST is considered as a non-superconducting reactor for use in the neutron irradiation facility. Conceptual design of the superconducting ST reactor is conducted in Japan and Korea independently. In the present article, the prospect of the ST reactor design is discussed. (author)

  12. Magnetic fusion energy research. Final report

    International Nuclear Information System (INIS)

    This report summarizes final work by the Plasma Theory Branch for the Department of Energy Magnetic Fusion Office under contract EX-76-A-34-1006. This report is divided into four parts. First, there is a final disposition of numerical codes developed under this contract. Second, there is a summary of work completed since the last annual report. Third, there is a series of final recommendations to the Department of Energy Magnetic Fusion Office. These recommendations generally concern: (a) transport, (b) MHD stability, and (c) heating

  13. Research and development toward realization of nuclear fusion power

    International Nuclear Information System (INIS)

    At National Institute for Fusion Science (NIFS), a part of National Institutes of Natural Sciences (NINS), conducts fundamental research of nuclear fusion power, which can generate energy from seawater. The research is centered on three main projects: (1) Large Helical Device (LHD) experiments, (2) computational simulations for experimental reactors, and (3) nuclear fusion engineering. This article introduces the basic principle of nuclear fusion power and the technologies that have been developed up to now, and then discusses future prospects. At first, in order to explain why human beings needs nuclear fusion power, the advantages of nuclear fusion power are described in comparison with other energy sources in terms of energy demand, available resources, carbon dioxide emission, and so on. Then, the current technological status of Helical method, which is being developed at our institute, and Tokamak method and other methods, which are being developed worldwide, as well as the reaction conditions for nuclear fusion are introduced. Furthermore, the future possibilities of nuclear fusion power mainly with Helical method but also with Tokamak method, as well as the outlook for the establishment of prototype reactor are discussed. (S.K.)

  14. Fusion research and technology records in INIS database

    International Nuclear Information System (INIS)

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

  15. Public Information in European Fusion Energy Research: Methods and Challenges

    Czech Academy of Sciences Publication Activity Database

    Mlynář, Jan; Kamendje, R.; Borba, D.; Antidormi, R.; Orlando, M.T.; Carpenter, C.; Casci, F.

    Mol: SCK-CEN the Belgian Nuclear Research Centre, 2005 - (Verboomen, B.; Ait Abderrahim, H.; D'Hondt, P.), s. 11-22 ISBN 907-69711-02. [12th International Conference on Emerging Nuclear Energy Systems – ICENES 2005. Brusel (BE), 21.08.2005-26.08.2005] Institutional research plan: CEZ:AV0Z20430508 Keywords : fusion * public information * fusion Expo * magnetic confinement Subject RIV: BL - Plasma and Gas Discharge Physics

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

    International Nuclear Information System (INIS)

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

  17. New era for fusion research centre

    CERN Multimedia

    Cartlidge, Edwin

    2003-01-01

    The former director general of CERN, Sir Chris Llewellyn Smith, takes over as director of the Culham fusion laboratory in Oxfordshire, UK. Plans for the laboratory include continuing the success of the Joint European Torus (JET) and the Mega Amp Spherical Tokamak (MAST) (1 page)

  18. 1983 Annual technical report on inertial fusion research

    International Nuclear Information System (INIS)

    An overview of the laser fusion program at KMS Fusion is presented. A two-beam laser (1053 nm and 527 nm) system is used for the implosion physics. Stimulated Raman scattering is used to examine the implosion region for high-energy electrons. Holographic and fringe analysis techniques are also used in the diagnostics of the plasma. Computational techniques based on two-plasmon decay are shock-fitting techniques in Lagrangian hydrocodes are also described. Glass shell technology for laser targets is given. The design of the Chemically Pumped Iodine Laser (CPIL) is also presented. 86 refs., 46 figs., 2 tabs

  19. High illumination uniformity scheme with 32 beams configuration for direct-drive inertial confinement fusion

    Science.gov (United States)

    Li, Li; Gu, Chun; Xu, Lixin; Zhou, Shenlei

    2016-04-01

    The self-adapting algorithms are improved to optimize a beam configuration in the direct drive laser fusion system with the solid state lasers. A configuration of 32 laser beams is proposed for achieving a high uniformity illumination, with a root-mean-square deviation at 10-4 level. In our optimization, the parameters such as beam number, beam arrangement, and beam intensity profile are taken into account. The illumination uniformity robustness versus the parameters such as intensity profile deviations, power imbalance, intensity profile noise, the pointing error, and the target position error is also discussed. In this study, the model is assumed a solid-sphere illumination, and refraction effects of incident light on the corona are not considered. Our results may have a potential application in the design of the direct-drive laser fusion of the Shen Guang-II Upgrading facility (SG-II-U, China).

  20. Research on Kalman-filter based multisensor data fusion

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    Multisensor data fusion has played a significant role in diverse areas ranging from local robot guidance to global military theatre defense etc.Various multisensor data fusion methods have been extensively investigated by researchers,of which Klaman filtering is one of the most important.Kalman filtering is the best-known recursive least mean-square algorithm to optimally estimate the unknown.states of a dynamic system,which has found widespread application in many areas.The scope of the work is restricted to investigate the various data fusion and track fusion techniques based on the Kalman Filter methods.then a new method of state fusion is proposed.Finally the simulation results demonstrate the effectiveness of the introduced method.

  1. Cold fusion research programs are in a bad way

    International Nuclear Information System (INIS)

    10 years ago S.Pons and M.Fleischmann announced that they had triggered a fusion reaction between deuterons in a lattice of palladium. This process was called cold fusion by S.Jones. Since then this field of investigation has been enlarged and numerous observations concerning chemically assisted nuclear reactions (RNCA) have been published. The author reviews the situation of cold fusion in research programs and it appears that major programs have been progressively abandoned throughout the world. 2 reasons can explain this lack of motivation, first the difficulties to establish reliable methods to reproduce cold fusion effects easily have favoured skeptics when financing budget was discussed, secondly the absence of evident commercial perspectives has been a powerful argument against cold fusion. (A.C.)

  2. Spin-off produced by the fusion research and development

    International Nuclear Information System (INIS)

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

  3. Materials research with neutron beams from a research reactor

    International Nuclear Information System (INIS)

    Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

  4. Materials research with neutron beams from a research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Root, J.; Banks, D. [Canadian Neutron Beam Centre, Chalk River Laboratories, Chalk River, Ontario (Canada)

    2015-03-15

    Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

  5. Heavy ion beam inertial confinement fusion studies in TIT

    International Nuclear Information System (INIS)

    The HICF studies in Tokyo Institute of Technology are focused on beam-plasma interaction and acceleration of intense ion beams by inductive and RF methods. Two types of plasma targets have been developed by means of Z-pinch discharge and laser irradiation for the interaction experiments. Measurements of energy loss and charge exchange of heavy ions are conducted with those plasma targets. An inductive acceleration of light ions has been initiated with a Mendel type plasma gun connected to a magnetic core cavity. An RFQ linac generates an intense helium beam of sharp rise in order that a beam-induced plasma can be studied. (orig.)

  6. 1981 inertial fusion research annual technical report

    International Nuclear Information System (INIS)

    This annual report consists of the following two topics: (1) target fabrication technology, and (2) fusion experiments. The first section is reported by the following seven areas: (1) characterization, (2) fuel shell technology, (3) polymer technology, (4) lithium foil development, (5) precision etch technology, (6) analytical instrumentation, and (7) target fabrication. The second area is reported by the following topics: (1) experiments, (2) plasma theory, (3) code development and simulation, and (4) lasers and optics

  7. Progress in Heavy Ion Driven Inertial Fusion Energy: From Scaled Experiments to the Integrated Research Experiment

    International Nuclear Information System (INIS)

    The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (approx 100's Amperes/beam) and ion energies (∼ 1 - 10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tun depressions, and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in the Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now beginning at LBNL. The mission of the HCX is to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned. The step which bridges the gap between the IBX and an engineering test facility for fusion has been designated the Integrated Research Experiment (IRE). The IRE (like the IBX) will provide an

  8. Progress in heavy ion driven inertial fusion energy: From scaled experiments to the integrated research experiment

    International Nuclear Information System (INIS)

    The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (∼100's Amperes/beam) and ion energies (∼1-10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions, and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now being constructed at LBNL. The mission of the HCX will be to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned. The step which bridges the gap between the IBX and an engineering test facility for fusion has been designated the Integrated Research Experiment (IRE). The IRE (like the IBX) will provide an

  9. Inertial confinement fusion experiments with OMEGA-A 30-kJ, 60-beam UV laser

    International Nuclear Information System (INIS)

    The Laboratory for Laser Energetics (LLE) experimental program supports the US inertial confinement fusion (ICF) effort by investigating the requirements for attaining ignition using direct drive targets. The primary tool for this research is OMEGA, a 60-beam, 351-nm, Nd:glass laser with an on-target energy capability in excess of 30 kJ. The laser is designed to ultimately achieve an irradiation uniformity of ∝1% on direct-drive capsules with shaped laser pulses (dynamic range >400:1). In addition, OMEGA provides unique capabilities for irradiating indirect-drive targets. This paper reports on a number of recent laser enhancements, including a new design for distributed phase plates (DPPs), two-dimensional smoothing by spectral dispersion (2-D SSD), distributed polarization rotators (DPRs) and laser pulse shaping. A variety of spherical implosion, planar-target, and indirect-drive experiments attest to the versatility of the OMEGA laser. A key result is the highest thermonuclear yield (1014 neutrons) and yield efficiency (1% of scientific breakeven) ever attained in laser fusion experiments. (orig.)

  10. Proton Beam Fast Ignition Fusion: Synergy of Weibel and Rayleigh-Taylor Instabilities

    Science.gov (United States)

    Stefan, V. Alexander

    2011-04-01

    The proton beam generation and focusing in fast ignition inertial confinement fusion is studied. The spatial and energy spread of the proton beam generated in a laser-solid interaction is increased due to the synergy of Weibel and Rayleigh-Taylor instabilities. The focal spot radius can reach 100 μm, which is nearly an order of magnitude larger than the optimal value. The energy spread decreases the beam deposition energy in the focal spot. Under these conditions, ignition of a precompressed DT fuel is achieved with the beam powers much higher than the values presently in consideration. Work supported in part by NIKOLA TESLA Laboratories (Stefan University), La Jolla, CA.

  11. Development and Testing of Atomic Beam-Based Plasma Edge Diagnostics in the CIEMAT Fusion Devices

    International Nuclear Information System (INIS)

    In this report the development of plasma edge diagnostic based on atomic beam techniques fir their application in the CIEMAT fusion devices is described. The characterisation of the beams in laboratory experiments at the CSIC, together with first results in the Torsatron TJ-II are reported. Two types of beam diagnostics have been developed: a thermal (effusive) Li and a supersonic, pulsed He beams. This work has been carried out in collaboration between the institutions mentioned above under partial financial support by EURATOM. (Author) 17 refs

  12. History, progress, achievement and future prospect of research activities on fusion materials by Japanese university researchers

    International Nuclear Information System (INIS)

    Research activities on fusion materials by Japanese university researchers are reviewed. Organized research on fusion materials has been initiated around mid 1970s under auspices of Monbusho (Ministry of Education, Science and Culture). Particularly effective was the Special Research Project on Fusion for fiscal year 1980 - 1989. At the same time, Japan/U.S. collaboration on fusion materials (1982 - 2000) has been very successful, yielding numerous useful results. The highlights of the technical achievement of these projects are briefly summarized. Both of these projects may be characterized to be composed of two major tasks, namely, fundamental aspects of alloy development for fusion and high fluence irradiation effects under fusion reactor environment. The basic philosophy of the project is discussed. The recent trend is to organize the university research activities into a comprehensive research network. (orig.)

  13. Methods of economic analysis applied to fusion research. Final report

    International Nuclear Information System (INIS)

    In this and previous efforts ECON has provided economic assessment of a fusion research program. This phase of study focused on two tasks, the first concerned with the economics of fusion in an economy that relies heavily upon synthetic fuels, and the second concerned with the overall economic effects of pursuing soft energy technologies instead of hard technologies. This report is organized in two parts, the first entitled An Economic Analysis of Coproduction of Fusion-Electric Energy and Other Products, and the second entitled Arguments Associated with the Choice of Potential Energy Futures

  14. Identifying heavy-ion-beam fusion design and system features with high economic leverage

    International Nuclear Information System (INIS)

    We have conducted parametric economic studies for heavy-ion-beam fusion electric power plants. We examined the effects on the cost of electricity of several design parameters: maximum achievable chamber pulse rate, driver cost, target gain, and electric conversion efficiency, and net electric power. We found with reasonable assumptions on driver cost, target gain, and electric conversion efficiency, a 2 to 3 GWe heavy-ion-beam fusion power plant, with a chamber pulse rate of 5 to 10 Hz, can be competitive with nuclear and coal power plants

  15. Identifying heavy-ion-beam fusion design and system features with high economic leverage

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-03-03

    We have conducted parametric economic studies for heavy-ion-beam fusion electric power plants. We examined the effects on the cost of electricity of several design parameters: maximum achievable chamber pulse rate, driver cost, target gain, and electric conversion efficiency, and net electric power. We found with reasonable assumptions on driver cost, target gain, and electric conversion efficiency, a 2 to 3 GWe heavy-ion-beam fusion power plant, with a chamber pulse rate of 5 to 10 Hz, can be competitive with nuclear and coal power plants.

  16. Ion beam requirements for fast ignition of inertial fusion targets

    CERN Document Server

    Honrubia, J J

    2015-01-01

    Ion beam requirements for fast ignition are investigated by numerical simulation taking into account new effects such as ion beam divergence not included before. We assume that ions are generated by the TNSA scheme in a curved foil placed inside a re-entrant cone and focused on the cone apex or beyond. From the focusing point to the compressed core ions propagate with a given divergence angle. Ignition energies are obtained for two compressed fuel configurations heated by proton and carbon ion beams. The dependence of the ignition energies on the beam divergence angle and on the position of the ion beam focusing point have been analysed. Comparison between TNSA and quasi-monoenergetic ions is also shown.

  17. New Capabilities for Modeling Intense Beams in Heavy Ion Fusion Drivers

    International Nuclear Information System (INIS)

    Significant advances have been made in modeling the intense beams of heavy-ion beam-driven Inertial Fusion Energy (Heavy Ion Fusion). In this paper, a roadmap for a validated, predictive driver simulation capability, building on improved codes and experimental diagnostics, is presented, as are examples of progress. The Mesh Refinement and Particle-in-Cell methods were integrated in the WARP code; this capability supported an injector experiment that determined the achievable current rise time, in good agreement with calculations. In a complementary effort, a new injector approach based on the merging of ∼100 small beamlets was simulated, its basic feasibility established, and an experimental test designed. Time-dependent 3D simulations of the High Current Experiment (HCX) were performed, yielding voltage waveforms for an upcoming study of bunch-end control. Studies of collective beam modes which must be taken into account in driver designs were carried out. The value of using experimental data to tomographically ''synthesize'' a 4D beam particle distribution and so initialize a simulation was established; this work motivated further development of new diagnostics which yield 3D projections of the beam phase space. Other developments, including improved modeling of ion beam focusing and transport through the fusion chamber environment and onto the target, and of stray electrons and their effects on ion beams, are briefly noted

  18. Approximations in fusion and breakup reactions induced by radioactive beams

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas, W.H.Z.; Carlin Filho, N.; Hussein, M.S. [Sao Paulo Univ., SP (Brazil). Inst. de Fisica; Canto, L.F.; Donangelo, R. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Inst. de Fisica; Lubian, J. [Universidade Federal Fluminense, Niteroi, RJ (Brazil). Inst. de Fisica; Centro de Aplicaciones Tecnologicas y Desarrollo Nuclear (CEADEN), Havana (Cuba); Romanelli, A. [Facultad de Ingenieria, Montevideo (Uruguay). Inst. de Fisica

    2000-07-01

    Some commonly used approximations for complete fusion and breakup transmission coefficients in collisions of weakly bound projectiles at near barrier energies are assessed. We show that they strongly depend on the adopted classical trajectory and can be significantly improved with proper treatment of the incident and emergent currents in the WKB approximation. (author)

  19. Nuclear Fusion: half a century of magnetic confinement research

    International Nuclear Information System (INIS)

    This book is written by physicists, whose distinguished carrers span most of the past half-century of fusion research. The book might be described as a scientific history. In giving a physicist's view of of fusion history, the authors are careful to document their souces, with twenty seven pages of references. They outline the roots of nuclear energy and plasma physics leading to the classification of fusion research and its declassification in 1958 in Geneva. Continuing from the profusion ideas disclosed at that time, they deal in succeding chapters with open systems, pulsed toroidal configurations and other alternatives, stellarators, and tokamaks. The concluding chapter, which is remarkably up to date, discusses the steps to a fusion reactor and th ehistory and status of ITER

  20. Nuclear Fusion: half a century of magnetic confinement research

    Energy Technology Data Exchange (ETDEWEB)

    Hutchinson, I.H

    2002-08-01

    This book is written by physicists, whose distinguished carrers span most of the past half-century of fusion research. The book might be described as a scientific history. In giving a physicist's view of of fusion history, the authors are careful to document their souces, with twenty seven pages of references. They outline the roots of nuclear energy and plasma physics leading to the classification of fusion research and its declassification in 1958 in Geneva. Continuing from the profusion ideas disclosed at that time, they deal in succeding chapters with open systems, pulsed toroidal configurations and other alternatives, stellarators, and tokamaks. The concluding chapter, which is remarkably up to date, discusses the steps to a fusion reactor and th ehistory and status of ITER.

  1. Heavy ion fusion accelerator research (HIFAR) year-end report, April 1, 1987-September 30, 1987

    International Nuclear Information System (INIS)

    The basic objective of the Heavy Ion Fusion Accelerator Research (HIFAR) program is to access the suitabilty of heavy ion accelerators as iginiters for Inertial Confinement Fusion (ICF). A specific accerelator techonolgy, the induction linac, has been studied at the Lawerence Berkeley Laboratory and has reached the point at which its viability for ICF applications can be assessed over the next few years. The HIFAR program addresses the generation of high-power, high-brightness beams of heavy ions, the understanding of the scaling laws in this novel physics regime, and the vadidation of new accelerator strategies, to cut costs. The papers in this report that address these goals are: MBE-4 mechanical progress, alignment of MBE-4, a compact energy analyzer for MBE-4, Cs+ injector modeling with the EGUN code, an improved emittance scanning system for HIFAR, 2-MV injector, carbon arc source development, beam combining in ILSE, emittance growth due to transverse beam combining in ILSE - particle simulation results, achromatic beam combiner for ILSE, additional elements for beam merging, quadrupole magnet design for ILSE, and waveforms and longitudinal beam-parameters for ILSE

  2. Heavy Ion Fusion Accelerator Research (HIFAR) half-year report, October 1, 1988--March 31, 1989

    International Nuclear Information System (INIS)

    The basic objective of the Heavy Ion Fusion Accelerator Research (HIFAR) program is to assess the suitability of heavy ion accelerators as igniters for Inertial Confinement Fusion (ICF). A specific accelerator technology, the induction linac, has been studied at the Lawrence Berkeley Laboratory and has reached the point at which its viability for ICF applications can be assessed over the next few years. The HIFAR program addresses the generation of high-power, high-brightness beams of heavy ions, the understanding of the scaling laws in this novel physics regime, and the validation of new accelerator strategies, to cut costs. Key elements to be addressed include: beam quality limits set by transverse and longitudinal beam physics; development of induction accelerating modules, and multiple-beam hardware, at affordable costs; acceleration of multiple beams with current amplification --both new features in a linac -- without significant dilution of the optical quality of the beams; and final bunching, transport, and accurate focusing on a small target

  3. Inertial confinement fusion research and development studies. Final report, October 1979-August 1980

    International Nuclear Information System (INIS)

    These Inertial Confinement Fusion (ICF) research and development studies were selected for structural, thermal, and vacuum pumping analyses in support of the High Yield Lithium Injection Fusion Energy (HYLIFE) concept development. An additional task provided an outlined program plan for an ICF Engineering Test Facility, using the HYLIFE concept as a model, although the plan is generally applicable to other ICF concepts. The HYLIFE is one promising type of ICF concept which features a falling array of liquid lithium jets. These jets surround the fusion reaction to protect the first structural wall (FSW) of the vacuum chamber by absorbing the fusion energy, and to act as the tritium breeder. The fusion energy source is a deuterium-tritium pellet injected into the chamber every second and driven by laser or heavy ion beams. The studies performed by Grumman have considered the capabilities of specific HYLIFE features to meet life requirements and the requirement to recover to preshot conditions prior to each subsequent shot. The components under investigation were the FSW which restrains the outward motion of the liquid lithium, the nozzle plate which forms the falling jet array, the graphite shield which is in direct top view of the fusion pellet, and the vacuum pumping system. The FSW studies included structural analysis, and definition of an experimental program to validate computer codes describing lithium motion and the resulting impact on the wall

  4. Fusion Research Center, theory program. Progress report

    International Nuclear Information System (INIS)

    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

  5. Heavy-ion fusion accelerator research, 1988

    International Nuclear Information System (INIS)

    This report discusses the following topics: MBE-4: The Induction-Linac Approach; Current Amplification and Acceleration Schedules; Emittance and Current Amplification; Scaling Up the Results; Progress on the Carbon-Arc Source; Injector Development; Progress Towards an ILSE Design; Beam Combination; and Focusing-System Alignment Tolerances

  6. Proof-of-Concept Experiments for Negative Ion Driver Beams for Heavy Ion Fusion

    International Nuclear Information System (INIS)

    Negative halogen ion beams have recently been proposed as heavy ion fusion drivers. They would avoid the problem of electron accumulation in positive ion beams, and could be efficiently photo-detached to neutrals if desired. Initial experiments using chlorine produced a current density of 45 mA/cm2 of 99.5% atomic negative Cl with an e/Cl- ratio as low as 7:1 and good emittance

  7. Transverse beam dynamics in recirculating accelerators for heavy-ion fusion

    International Nuclear Information System (INIS)

    A conceptual design for a circular induction accelerator has been proposed as a driver for heavy-ion fusion. In such an accelerator, errors in dipole strength and quadrupole alignment affect the transverse motion of the beam centroid. Analytic and numerical estimates are made of the beam-centroid displacement due to these errors, and a steering algorithm to correct the transverse mismatch from these errors is described and tested numerically

  8. Negative-ion-based neutral beams for fusion

    International Nuclear Information System (INIS)

    To maximize the usefulness of an engineering test reactor (e.g., ITER, TIBER), it is highly desirable that it operate under steady-state conditions. The most attractive option for maintaining the circulating current needed in the center of the plasma is the injection of powerful beams of neutral deuterium atoms. The beam simultaneously heats the plasma. At the energies required, in excess of 500 keV, such beams can be made by accelerating D- ions and then removing the electron. Sources are being developed that generate the D- ions in the volume of a specially constructed plasma discharge, without the addition of cesium. These sources must operate with minimum gas flow, to avoid stripping the D- beam, and with minimum electron output. We are designing at LBL highly efficient electrostatic accelerators that combine electric strong-focusing with dc acceleration and offer the possibility of varying the beam energy at constant current while minimizing breakdown. Some form of rf acceleration may also be required. To minimize irradiation of the ion sources and accelerators, the D- beam can be transported through a maze in the neutron shielding. The D- ions can be converted to neutrals in a gas or plasma target, but advances in laser and mirror technology may make possible very efficient photodetachment systems by the time an ETR becomes operational. 9 refs., 4 figs

  9. Ionization, stopping, and thermalization of hydrogen and boron beams injected in fusion plasmas

    Science.gov (United States)

    Lifschitz, Agustín F.; Farengo, Ricardo; Arista, Nestor R.

    2000-07-01

    The ionization, stopping, and thermalization of hydrogen and boron beams, injected, respectively, in boron and hydrogen plasmas, is studied. The evolution of the charge state populations of the neutral beams is described considering the various ionization, excitation, and charge exchange channels. The interaction of the beam with the plasma is described in terms of the Fokker-Planck equation, which is numerically solved to show in detail the evolution of the beam until final thermalization is reached. Beam energies of 640 keV/u (maximum of the cross section for the p-B11 fusion reaction) and 200 keV/u, and various plasma temperatures are considered. It is seen that, due to an important perpendicular-diffusion effect, high energy beams reach effective peak temperatures which are much higher than the plasma temperature, before equilibrium is established. The fraction of fusioned particles is also calculated. Some implications of interest for recently proposed p-B11 fusion reactor systems are drawn out.

  10. Novel neutralized-beam intense neutron source for fusion technology development

    International Nuclear Information System (INIS)

    We describe a neutralized-beam intense neutron source (NBINS) as a relevant application of fusion technology for the type of high-current ion sources and neutral beamlines now being developed for heating and fueling of magnetic-fusion-energy confinement systems. This near-term application would support parallel development of highly reliable steady-state higher-voltage neutral D0 and T0 beams and provide a relatively inexpensive source of fusion neutrons for materials testing at up to reactor-like wall conditions. Beam-target examples described incude a 50-A mixed D-T total (ions plus neutrals) space-charge-neutralized beam at 120 keV incident on a liquid Li drive-in target, or a 50-A T0 + T+ space-charge-neutralized beam incident on either a LiD or gas D2 target with calculated 14-MeV neutron yields of 2 x 1015/s, 7 x 1015/s, or 1.6 x 1016/s, respectively. The severe local heat loading on the target surface is expected to limit the allowed beam focus and minimum target size to greater than or equal to 25 cm2

  11. TFTR [Tokamak Fusion Test Reactor] neutral beam injected power measurement

    International Nuclear Information System (INIS)

    Energy flow within TFTR neutral beamlines is measured with a waterfall calorimetry system capable of simultaneously measuring the energy deposited within four heating beamlines (three ion sources each), or of measuring the energy deposited in a separate neutral beam test stand. Of the energy extracted from the ion source in the well instrumented test stand, 99.5 +- 3.5% can be accounted for. When the ion deflection magnet is energized, however, 6.5% of the extracted energy is lost. This loss is attributed to a spray of devious particles onto unmonitored surfaces. A 30% discrepancy is also observed between energy measurements on the internal beamline calorimeter and energy measurements on a calorimeter located in the test stand target chamber. Particle reflection from the flat plate calorimeter in the target chamber, which the incident beam strikes at a near-grazing angle of 12/degree/, is the primary loss of this energy. A slight improvement in energy accountability is observed as the beam pulse length is increased. This improvement is attributed to systematic error in the sensitivity of the energy measurement to small fluctuations on the supply water temperature. An overall accuracy of 15% is estimated for the total power injected into TFTR. Contributions to this error are uncertainties in the beam neutralization efficiency, reionization and beam scrape-off in the drift duct, and fluctuations in the temperature of the supply water. 28 refs., 9 figs., 1 tab

  12. Light ion beams as the driver for inertial confinement fusion

    International Nuclear Information System (INIS)

    Because of the high costs associated with producing the > or approx. =1 MJ, 10 ns pulse required to initiate a pellet, the efficiency and relatively low cost of pulse power driven ion beams makes this approach particularly attractive both for proof-of-principle and for reactors in the future. Although pulse power technology for producing multimegavolt and multimegampere electric pulses is well-established, the coupling of this energy into ion beams focused onto targets requires further work. During the last six years, focused ion beam intensity has been improved more than five orders of magnitude to a value of approx.1012 W/cm2. An additional factor of 40 in focused power density will be required; this will be provided by the PBFA II accelerator now being designed and scheduled for completion in 1985. This paper will briefly describe how pulse power systems deliver energy to ion sources, how beams are generated and focused, and a few examples of target irradiation experiments. Finally, a concept for delivering beams to pellets in the center of a reactor wall will be described

  13. Summary of Progress in US Heavy Ion Fusion Science Research

    International Nuclear Information System (INIS)

    Full text: Construction of the Neutralized Drift Compression eXperiment (NDCX-II), a new high- current, moderate-kinetic-energy accelerator facility at LBNL, is being completed in the spring of 2012. The machine will produce a nanosecond Li+ ion beam bunch at ∼ 2 MeV energy for volumetric heating of thin foils. Extensive simulations using the Warp code led to a physics design with specialized acceleration voltage waveforms that can achieve > 500-fold longitudinal beam compression. Planned experiments on NDCX-II to study warm dense matter include: measuring equation of state and phase transitions, conductivity, opacity and shock generation. Theoretically, we have: 1. Studied transverse and longitudinal beam compression on two-stream interactions of an intense ion beam in plasma. 2. Studied transverse gradients and profile shapes on beam-plasma instabilities. 3. Identified a class of self-consistent periodic kinetic “equilibria” for intense beams in alterna- ting-gradient focusing systems, and extended nonlinear perturbative particle simulations to such focusing systems. 4. Investigated nonlinear effects of beam-plasma instabilities on beam current neutralization. 5. Proposed a Rayleigh-Taylor instability mechanism for droplet formation in expanding warm dense matter. 6. Carried out theoretical studies of using a beam “wobbler” (periodic deflector) as a beam smoothing technique. Using HYDRA simulations to design the novel Heavy Ion Fusion X-target, it was found that, by adding an aluminum pusher and radial tamping, the fusion gain can be increased from 50 to 300, and the stagnation fuel density doubled to 100 g/cm3 at peak compression, with a ρr „ 2 g/cm2. The X-target has a simple cylindrical metal case filled with DT fuel and a conical insert with an “X” shaped cross-section. Using multiple heavy ion beams to illuminate the target axially from only one side, the fuel can be compressed and ignited at the X-vertex. The simulations showed negligible

  14. Ion implantation applied to fusion research

    International Nuclear Information System (INIS)

    Ion implantation and microanalysis have been used to investigate plasma-surface interactions relevant to fusion applications. Previous results for pure metals are reviewed and current results are presented for TiB2 and B4C coatings for tokamak surfaces. Enhanced trapping of implanted, low-energy hydrogen has been shown to occur at room temperature in W, Au, Pd, Mo, Nb, TiB2, and B4C for He or other ion predamage. Hydrogen depth profiles obtained using 1H(19F, αγ)16O resonant nuclear reaction show that the H decorates the He damage profiles at traps whose concentration is proportional to the amount of He-induced damage

  15. Induction-accelerator heavy-ion fusion: Status and beam physics issues

    International Nuclear Information System (INIS)

    Inertial confinement fusion driven by beams of heavy ions is an attractive route to controlled fusion. In the U.S., induction accelerators are being developed as open-quote open-quote drivers close-quote close-quote for this process. This paper is divided into two main sections. In the first section, the concept of induction-accelerator driven heavy-ion fusion is briefly reviewed, and the U.S. program of experiments and theoretical investigations is described. In the second, a open-quote open-quote taxonomy close-quote close-quote of space-charge-dominated beam physics issues is presented, accompanied by a brief discussion of each area. copyright 1996 American Institute of Physics

  16. Study of ion beam-initiated inertial-confinement fusion. Final report, January 1, 1981-December 31, 1981

    International Nuclear Information System (INIS)

    For the past four years, Occidental Research Corporation has been conducting a fusion program which is based on a reactor concept in which geometrically focused and time compressed beams of cold light ions and neutralizing cold electrons from large area sources are ballistically propagated over several meters through a near vacuum to implode a pellet target. The approach combines the cost advantage of efficient moderate voltage pulsed power technology with the simplicity-advantage of unguided ballistic propagation. In addition, the compactness, efficiency, focusability and energy range of the system makes the approach of great interest for supplementary heating of magnetically confined fusion plasmas. Theoretical analyses have been made of beam-target interaction, beam progagation and source accelerator design. A one-dimensional implosion and nuclear burn code indicates that significant yields can be obtained from simple targets with moderately energetic light ions. Experimentally the short-term objective is to demonstrate that the required degree of space-time focusing can be achieved on a 200-500 keV electron neutralized ion (or plasma) beam from a simple prototype 100 sq cm low temperature zeolite source

  17. NIFS symposium: toward the research of fusion burning plasmas

    International Nuclear Information System (INIS)

    NIFS symposium, entitled 'Toward the research of Fusion Burning Plasmas - Present status and Future Strategy' was held at NIFS on July 15th 1992. This NIFS symposium covers various topics related to burning plasma, e.g., JET DT experiment, Plan for DT experiment on TFTR as well as the future trends among researchers. To study the critical issues and trends of future research, a questionnaire was sent to about 100 researchers. This report presents such activities in the NIFS symposium. (author)

  18. Modeling crossed-beam energy transfer for inertial confinement fusion

    Science.gov (United States)

    Marion, D. J. Y.; Debayle, A.; Masson-Laborde, P.-E.; Loiseau, P.; Casanova, M.

    2016-05-01

    We developed a numerical code that describes both the energy transfer occurring when two or more laser beams overlap in a weakly non-homogeneous plasma, and the beam energy losses associated with the electron-ion collisions. The numerical solutions are validated with both the exact analytical solutions in homogeneous plasmas, and with new approximate analytical solutions in non-homogeneous plasmas that include the aforementioned inverse bremsstrahlung effect. Comparisons with kinetic particle-in-cell simulations are satisfactory, provided the acoustic wave-breaking limit and the self-focusing regime are not reached. An application of the Cross-Beam Energy Transfer model is shown for a typical case of indirect-drive implosion in a gold hohlraum.

  19. National facility for neutron beam research

    Indian Academy of Sciences (India)

    K R Rao

    2004-07-01

    In this talk, the growth of neutron beam research (NBR) in India over the past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview of current scenario of NBR world-wide and future of Indian activities.

  20. Fusion reactions initiated by laser-accelerated particle beams in a laser-produced plasma

    CERN Document Server

    Labaune, C; Depierreux, S; Goyon, C; Loisel, G; Yahia, V; Rafelski, J

    2013-01-01

    The advent of high-intensity pulsed laser technology enables the generation of extreme states of matter under conditions that are far from thermal equilibrium. This in turn could enable different approaches to generating energy from nuclear fusion. Relaxing the equilibrium requirement could widen the range of isotopes used in fusion fuels permitting cleaner and less hazardous reactions that do not produce high energy neutrons. Here we propose and implement a means to drive fusion reactions between protons and boron-11 nuclei, by colliding a laser-accelerated proton beam with a laser-generated boron plasma. We report proton-boron reaction rates that are orders of magnitude higher than those reported previously. Beyond fusion, our approach demonstrates a new means for exploring low-energy nuclear reactions such as those that occur in astrophysical plasmas and related environments.

  1. Fusion reactions initiated by laser-accelerated particle beams in a laser-produced plasma

    International Nuclear Information System (INIS)

    The advent of high-intensity-pulsed laser technology enables the generation of extreme states of matter under conditions that are far from thermal equilibrium. This in turn could enable different approaches to generating energy from nuclear fusion. Relaxing the equilibrium requirement could widen the range of isotopes used in fusion fuels permitting cleaner and less hazardous reactions that do not produce high-energy neutrons. Here we propose and implement a means to drive fusion reactions between protons and boron-11 nuclei by colliding a laser-accelerated proton beam with a laser-generated boron plasma. We report proton-boron reaction rates that are orders of magnitude higher than those reported previously. Beyond fusion, our approach demonstrates a new means for exploring low-energy nuclear reactions such as those that occur in astrophysical plasmas and related environments. (authors)

  2. Spectrum analysis of hydrogen plasma in spherically convergent beam fusion

    International Nuclear Information System (INIS)

    Spectroscopic analysis of spherical glow discharge fusion device was carried out using hydrogen gas. Effects of the discharge current and cathode voltage on spectrum profiles of hydrogen Balmar lines were measured. The profiles of all hydrogen lines were broadened with the cathode voltage. From the relationship between the maximum broadening width and the cathode voltage, it was indicated that the broadening was caused by the Doppler effect. From the spatial distribution of emission intensity, it was found that plasma core size became larger with discharge current and smaller with cathode voltage. (author)

  3. Spectrum analysis of hydrogen plasma in spherically convergent beam fusion

    Energy Technology Data Exchange (ETDEWEB)

    Ogasawara, Kazuki; Yamauchi, Kunihito; Watanabe, Masato; Sunaga, Yoshitaka; Hotta, Eiki [Tokyo Institute of Technology, Dept. of Energy Sciences, Yokohama, Kanagawa (Japan); Okino, Akitoshi [Tokyo Institute of Technology, Dept. of Electrical and Electronic Engineering, Tokyo (Japan)

    2001-09-01

    Spectroscopic analysis of spherical glow discharge fusion device was carried out using hydrogen gas. Effects of the discharge current and cathode voltage on spectrum profiles of hydrogen Balmar lines were measured. The profiles of all hydrogen lines were broadened with the cathode voltage. From the relationship between the maximum broadening width and the cathode voltage, it was indicated that the broadening was caused by the Doppler effect. From the spatial distribution of emission intensity, it was found that plasma core size became larger with discharge current and smaller with cathode voltage. (author)

  4. Annual report of Fusion Research and Development Directorate of JAEA

    International Nuclear Information System (INIS)

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2007 to March 31, 2008, including those performed in collaboration with other directorates of JAEA, research institutes, and universities. The JT-60U operation regime was extended toward the long sustainment of high normalized beta (βN) with good confinement (βN=2.6 x 28 s). Effectiveness of real-time control of current profile was demonstrated in high β plasmas. Toroidal momentum diffusivity and the convection velocity were systematically clarified for the first time, and intrinsic rotation due to pressure gradient was discovered. Effects of toroidal rotation and magnetic field ripple on type 1 ELM size and pedestal performance were clarified, and type I ELM control was demonstrated by toroidal rotation control. Variety of inter-machine experiments, such as JT-60U and JET, and domestic collaborations were performed. In theoretical and analytical researches, for the NEXT (Numerical Experiment of Tokamak) project, numerical simulations of a tokamak plasma turbulence progressed and a zonal field generation was investigated. Also, nonlinear MHD simulations found the Alfven resonance effects on the evolution of magnetic islands driven by externally applied perturbations. Integrations of several kinds of element codes progressed in the integrated transport/MHD model, the integrated edge/pedestal model and the integrated SOL/divertor model. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 800 s with 1 MW was demonstrated. Also extracted beam current of the neutral beam injector has been extended to 320 mA at 796 keV. In the ITER Test Blanket Module (TBM), designs and R and Ds on Water and Helium Cooled Solid Breeder TBMs were progressed. For the

  5. Looking back at half a century of fusion research

    International Nuclear Information System (INIS)

    This article gives a short overview of the origins of nuclear fusion and of its development as a potential source of terrestrial energy. The main milestones of the fusion history are: -) the Einstein's prediction that mass can be converted into energy; -) the complete understanding of the main fusion reactions in the sun and stars in late 1920; -) many different magnetic configurations were proposed in the early years of fusion research: the earliest magnetic confinement devices in the U.K were toroidal pinches, the stellarator was invented in the U.S.A and the helical heliotron in Japan ; -) the success of the Russian tokamak T-3 to produce hot enough plasmas opened the way to the construction of very large tokamaks: JET (U.K), TFTR (Usa), JT-60 (Japan) and Tore-supra (France); -) an alternative approach to fusion: the inertial confinement; and -) the ITER project. After many years, the scientific feasibility of thermonuclear fusion via the magnetic confinement route has been demonstrated and the next generation of inertial confinement experiments is expected to reach a similar position. (A.C.)

  6. Thermonuclear Fusion Research Progress and the Way to the Reactor

    Science.gov (United States)

    Koch, Raymond

    2006-06-01

    The paper reviews the progress of fusion research and its prospects for electricity generation. It starts with a reminder of the principles of thermonuclear fusion and a brief discussion of its potential role in the future of the world energy production. The reactions allowing energy production by fusion of nuclei in stars and on earth and the conditions required to sustain them are reviewed. At the high temperatures required for fusion (hundred millions kelvins), matter is completely ionized and has reached what is called its 4th state: the plasma state. The possible means to achieve these extreme temperatures is discussed. The remainder of the paper focuses on the most promising of these approaches, magnetic confinement. The operating principles of the presently most efficient machine of this type — the tokamak — is described in some detail. On the road to producing energy with fusion, a number of obstacles have to be overcome. The plasma, a fluid that reacts to electromagnetic forces and carries currents and charges, is a complex medium. Fusion plasma is strongly heated and is therefore a good example of a system far from equilibrium. A wide variety of instabilities can grow in this system and lead to self-organized structures and spontaneous cycles. Turbulence is generated that degrades the confinement and hinders easy achievement of long lasting hot plasmas. Physicists have learned how to quench turbulence, thereby creating sort of insulating bottles inside the plasma itself to circumvent this problem. The recent history of fusion performance is outlined and the prospect of achieving power generation by fusion in a near future is discussed in the light of the development of the "International Tokamak Experimental Reactor" project ITER.

  7. Thermonuclear Fusion Research Progress and the Way to the Reactor

    International Nuclear Information System (INIS)

    The paper reviews the progress of fusion research and its prospects for electricity generation. It starts with a reminder of the principles of thermonuclear fusion and a brief discussion of its potential role in the future of the world energy production. The reactions allowing energy production by fusion of nuclei in stars and on earth and the conditions required to sustain them are reviewed. At the high temperatures required for fusion (hundred millions kelvins), matter is completely ionized and has reached what is called its 4th state: the plasma state. The possible means to achieve these extreme temperatures is discussed. The remainder of the paper focuses on the most promising of these approaches, magnetic confinement. The operating principles of the presently most efficient machine of this type -- the tokamak -- is described in some detail. On the road to producing energy with fusion, a number of obstacles have to be overcome. The plasma, a fluid that reacts to electromagnetic forces and carries currents and charges, is a complex medium. Fusion plasma is strongly heated and is therefore a good example of a system far from equilibrium. A wide variety of instabilities can grow in this system and lead to self-organized structures and spontaneous cycles. Turbulence is generated that degrades the confinement and hinders easy achievement of long lasting hot plasmas. Physicists have learned how to quench turbulence, thereby creating sort of insulating bottles inside the plasma itself to circumvent this problem. The recent history of fusion performance is outlined and the prospect of achieving power generation by fusion in a near future is discussed in the light of the development of the 'International Tokamak Experimental Reactor' project ITER

  8. Annual progress report 1993. Work in controlled thermonuclear fusion research performed in the fusion research unit under the contract of association between Euratom and Risoe National Laboratory

    International Nuclear Information System (INIS)

    The programme of the Research Unit of the Fusion Association Euratom-Risoe National Laboratory covers work in fusion plasma physics and in fusion technology. The fusion plasma physics group has activities within (a) studies of nonlinear dynamical processes in magnetized plasmas, (b) development of pellet injectors for fusion experiments, and (c) development of diagnostics for fusion plasmas. The activities in technology cover radiation damage of fusion reactor materials. A summary of the activities in 1993 is presented. (au) (4 tabs., 21 ills., 64 refs.)

  9. Three-dimensional particle simulation of heavy-ion fusion beams

    International Nuclear Information System (INIS)

    The beams in a heavy-ion-beam-driven inertial fusion (HIF) accelerator are collisionless, nonneutral plasmas, confined by applied magnetic and electric fields. These space-charge-dominated beams must be focused onto small (few mm) spots at the fusion target, and so preservation of a small emittance is crucial. The nonlinear beam self-fields can lead to emittance growth, and so a self-consistent field description is needed. To this end, a multidimensional particle simulation code, WARP [Friedman et al., Part. Accel. 37-38, 131 (1992)], has been developed and is being used to study the transport of HIF beams. The code's three-dimensional (3-D) package combines features of an accelerator code and a particle-in-cell plasma simulation. Novel techniques allow it to follow beams through many accelerator elements over long distances and around bends. This paper first outlines the algorithms employed in WARP. A number of applications and corresponding results are then presented. These applications include studies of: beam drift-compression in a misaligned lattice of quadrupole focusing magnets; beam equilibria, and the approach to equilibrium; and the MBE-4 experiment [AIP Conference Proceedings 152 (AIP, New York, 1986), p. 145] recently concluded at Lawrence Berkeley Laboratory (LBL). Finally, 3-D simulations of bent-beam dynamics relevant to the planned Induction Linac Systems Experiments (ILSE) [Fessenden, Nucl. Instrum. Methods Plasma Res. A 278, 13 (1989)] at LBL are described. Axially cold beams are observed to exhibit little or no root-mean-square emittance growth at midpulse in transiting a (sharp) bend. Axially hot beams, in contrast, do exhibit some emittance growth

  10. Multi-Sampling Ionization Chamber (MUSIC) for measurements of fusion reactions with radioactive beams

    Energy Technology Data Exchange (ETDEWEB)

    Carnelli, P.F.F. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Laboratorio TANDAR, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, B1650KNA, San Martín, Buenos Aires (Argentina); Consejo Nacional de Investigaciones Científicas y Técnicas, Av. Rivadavia 1917, C1033AAJ Buenos Aires (Argentina); Almaraz-Calderon, S. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Rehm, K.E., E-mail: rehm@anl.gov [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Albers, M.; Alcorta, M.; Bertone, P.F.; Digiovine, B.; Esbensen, H. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Fernández Niello, J. [Laboratorio TANDAR, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, B1650KNA, San Martín, Buenos Aires (Argentina); Universidad Nacional de San Martín, Campus Miguelete, B1650BWA San Martín, Buenos Aires (Argentina); Henderson, D.; Jiang, C.L. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Lai, J. [Department of Physics and Astronomy, Louisiana State University, Baton Rouge, LA 70803 (United States); Marley, S.T.; Nusair, O.; Palchan-Hazan, T.; Pardo, R.C. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States); Paul, M. [Racah Institute of Physics, Hebrew University, Jerusalem (Israel); Ugalde, C. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States)

    2015-11-01

    A detection technique for high-efficiency measurements of fusion reactions with low-intensity radioactive beams was developed. The technique is based on a Multi-Sampling Ionization Chamber (MUSIC) operating as an active target and detection system, where the ionization gas acts as both target and counting gas. In this way, we can sample an excitation function in an energy range determined by the gas pressure, without changing the beam energy. The detector provides internal normalization to the incident beam and drastically reduces the measuring time. In a first experiment we tested the performance of the technique by measuring the {sup 10,13,15}C+{sup 12}C fusion reactions at energies around the Coulomb barrier.

  11. Multi-Sampling Ionization Chamber (MUSIC) for measurements of fusion reactions with radioactive beams

    International Nuclear Information System (INIS)

    A detection technique for high-efficiency measurements of fusion reactions with low-intensity radioactive beams was developed. The technique is based on a Multi-Sampling Ionization Chamber (MUSIC) operating as an active target and detection system, where the ionization gas acts as both target and counting gas. In this way, we can sample an excitation function in an energy range determined by the gas pressure, without changing the beam energy. The detector provides internal normalization to the incident beam and drastically reduces the measuring time. In a first experiment we tested the performance of the technique by measuring the 10,13,15C+12C fusion reactions at energies around the Coulomb barrier

  12. Study on advanced cancer treatment method using quantum beam fusion technology

    International Nuclear Information System (INIS)

    This study on advanced cancer treatment method using quantum beam fusion technology aims at the realization of the fusion therapy device between boron neutron capture therapy device and THz wave hyperthermia device. To achieve this purpose, it is necessary to develop an intra-body transmission technology of THz beams. From the transmission experiment of 0.2 THz wave using sapphire microfiber, it has been found that the transmission of THz microbeam into the intra-body cancer affected part is possible. As the technologies to commercially realize the intra-body transmission of THz beams, this paper describes the coupler for transmission, flexible corrugated horn, and the micro-fabrication techniques of microfibers. In addition, the authors conducted the development of an optical fiber type rotary encoder for the long-distance transmission of THz waves, and confirmed that the effects of vibration did not exist through the evaluation of vibration durability. (A.O.)

  13. Multi-Sampling Ionization Chamber (MUSIC) for measurements of fusion reactions with radioactive beams

    Science.gov (United States)

    Carnelli, P. F. F.; Almaraz-Calderon, S.; Rehm, K. E.; Albers, M.; Alcorta, M.; Bertone, P. F.; Digiovine, B.; Esbensen, H.; Fernández Niello, J.; Henderson, D.; Jiang, C. L.; Lai, J.; Marley, S. T.; Nusair, O.; Palchan-Hazan, T.; Pardo, R. C.; Paul, M.; Ugalde, C.

    2015-11-01

    A detection technique for high-efficiency measurements of fusion reactions with low-intensity radioactive beams was developed. The technique is based on a Multi-Sampling Ionization Chamber (MUSIC) operating as an active target and detection system, where the ionization gas acts as both target and counting gas. In this way, we can sample an excitation function in an energy range determined by the gas pressure, without changing the beam energy. The detector provides internal normalization to the incident beam and drastically reduces the measuring time. In a first experiment we tested the performance of the technique by measuring the 10,13,15C+12C fusion reactions at energies around the Coulomb barrier.

  14. Response to FESAC survey, non-fusion connections to Fusion Energy Sciences. Applications of the FES-supported beam and plasma simulation code, Warp

    International Nuclear Information System (INIS)

    The Fusion Energy Sciences Advisory Committee's subcommittee on non-fusion applications (FESAC NFA) is conducting a survey to obtain information from the fusion community about non-fusion work that has resulted from their DOE-funded fusion research. The subcommittee has requested that members of the community describe recent developments connected to the activities of the DOE Office of Fusion Energy Sciences. Two questions in particular were posed by the subcommittee. This document contains the authors' responses to those questions.

  15. Response to FESAC survey, non-fusion connections to Fusion Energy Sciences. Applications of the FES-supported beam and plasma simulation code, Warp

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Grote, D. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Vay, J. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-05-29

    The Fusion Energy Sciences Advisory Committee’s subcommittee on non-fusion applications (FESAC NFA) is conducting a survey to obtain information from the fusion community about non-fusion work that has resulted from their DOE-funded fusion research. The subcommittee has requested that members of the community describe recent developments connected to the activities of the DOE Office of Fusion Energy Sciences. Two questions in particular were posed by the subcommittee. This document contains the authors’ responses to those questions.

  16. Plasma physics and controlled nuclear fusion research 1990. V. 3

    International Nuclear Information System (INIS)

    The thirteenth International Atomic Energy Agency Conference on Plasma Physics and Controlled Nuclear Fusion Research, held in Washington D.C., 1-6 October 1990, and organized in cooperation with the United States Department of Energy, was devoted to the exchange and dissemination of reports on the steady progress in the research on both inertial and magnetic confinement fusion, aiming ultimately for the production of commercial energy from controlled thermonuclear reactors. More than two hundred technical papers presented work on tokamak experiments, inertial confinement, non-tokamak confinement systems, magnetic confinement theory and modelling, plasma heating and current drive, the ITER project, technology and reactor concepts, and the economic, safety and environmental aspects of thermonuclear fusion. Refs, figs and tabs

  17. Reviewers Comments on the 5th Symposium and the Status of Fusion Research 2003

    Energy Technology Data Exchange (ETDEWEB)

    Post, R F

    2005-02-03

    Better to understand the status of fusion research in the year 2003 we will first put the research in its historical context. Fusion power research, now beginning its sixth decade of continuous effort, is unique in the field of scientific research. Unique in its mixture of pure and applied research, unique in its long-term goal and its promise for the future, and unique in the degree that it has been guided and constrained by national and international governmental policy. Though fusion research's goal has from the start been precisely defined, namely, to obtain a net release of energy from controlled nuclear fusion reactions between light isotopes (in particular those of hydrogen and helium) the difficulty of the problem has spawned in the past a very wide variety of approaches to the problem. Some of these approaches have had massive international support for decades, some have been pursued only at a ''shoestring'' level by dedicated groups in small research laboratories or universities. In discussing the historical and present status of fusion research the implications of there being two distinctly different approaches to achieving net fusion power should be pointed out. The first, and oldest, approach is the use of strong magnetic fields to confine the heated fuel, in the form of a plasma and at a density typically four or five orders of magnitude smaller than the density of the atmosphere. In steady state this fusion fuel density is still sufficient to release fusion energy at the rate of many megawatts per cubic meter. The plasma confinement times required for net energy release in this regime are long--typically a second or more, representing an extremely difficult scientific challenge --witness the five decades of research in magnetic fusion, still without having reaching that goal. The second, more recently initiated approach, is of course the ''inertial'' approach. As its name implies, the &apos

  18. Closing summary for inertial confinement fusion, diodes and beam transport

    International Nuclear Information System (INIS)

    The progress since BEAMS'83 has been very encouraging. The experiments and theories are of significantly higher quality than we have seen in the past. The problems that have been identified in our fields are now being solved. Scientific comradery is improving and more scientists from different countries are working to complement their associates on similar projects in other countries. The papers presented at this conference have been much more substantial scientifically than in the past and indicate the maturation of our discipline

  19. Electron-temperature requirements for neutralized inertial-confinement-fusion light-ion beams

    International Nuclear Information System (INIS)

    Because of their large self-space-charge fields, light ion beam drivers of energy and power sufficient to achieve inertial confinement fusion (ICF) cannot be focused on a small fuel pellet unless neutralized. Even if initially neutralized with comoving electrons, these beams will not stay neutralized and focus during propagation through a vacuum chamber unless the initial thermal energy of the neutralizing electrons is sufficiently small. In this paper we discuss the effects which contribute to the effective initial temperature of the neutralizing electrons, including compressional shock heating. We also employ a simple heuristic model to construct envelope equations which govern axial as well as radial beam compression and use them to predict the largest initial electron temperature consistent with the required beam compression. This temperature for typical light ion beam systems is about ten eV - a temperature which may be possible to achieve

  20. ITER implementation and fusion energy research in China

    International Nuclear Information System (INIS)

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

  1. Inertial confinement fusion research at Imperial College

    International Nuclear Information System (INIS)

    The paper summarizes experimental and theoretical work relevant to inertial confinement fusion. A quantitative study of laser imprinting and subsequent Rayleigh-Taylor (R-T) growth of directly driven planar, solid, thin foil targets has been carried out. The experimental results are well reproduced by two and three dimensional radiation transport hydrodynamics simulations. The reduction of the hydrodynamic target breakup due to imprinting was investigated for several laser and target conditions on targets which were overcoated with a low density foam jacket facing the incident laser radiation. The shock in the foam produced by laser ablation, and the density and temperature profiles of the shocked material generated in the foam, were measured. The preheating in solid targets caused by the shock and the radiation wave was measured on targets with and without foam overcoats. Measurements were carried out of the R-T instability in planar modulated foil targets driven by soft X ray radiation emitted from a laser heated hohlraum. This allowed the Takabe-Morse rollover due to ablative stabilization to be investigated. Mode coupling was studied by using modulated targets with several short wavelength modes. A new multimode coupling model of the R-T instability was developed. An analytical model was developed which describes the saturation of self generated magnetic fields in laser produced plasmas. Finally, short pulse, high intensity experiments were carried out to study some aspects of the fast ignitor concept. In particular, the propagation of a short laser pulse at relativistic intensities through an underdense plasma was studied. (author)

  2. Contribution to fusion research from IAEA coordinated research projects and joint experiments

    Science.gov (United States)

    Gryaznevich, M.; Van Oost, G.; Stöckel, J.; Kamendje, R.; Kuteev, B. N.; Melnikov, A.; Popov, T.; Svoboda, V.; The IAEA CRP Teams

    2015-10-01

    The paper presents objectives and activities of IAEA Coordinated Research Projects ‘Conceptual development of steady-state compact fusion neutron sources’ and ‘Utilisation of a network of small magnetic confinement fusion devices for mainstream fusion research’. The background and main projects of the CRP on FNS are described in detail, as this is a new activity at IAEA. Recent activities of the second CRP, which continues activities of previous CRPs, are overviewed.

  3. Plasma physics and controlled nuclear fusion research 1990. V. 2

    International Nuclear Information System (INIS)

    Volume 2 of the Proceedings of the Thirteenth International Conference on Plasma Physics and Controlled Fusion Research contains papers in two sessions: the first part, on Magnetic Confinement Theory and Modelling, was presented in session D at the conference; the second part, on Non-Tokamak Confinement Systems, was given in session C of the conference. Abstracts accompany each paper. Refs, figs and tabs

  4. Fusion research and third world countries

    International Nuclear Information System (INIS)

    The Egypt experience in the plasma researches, asking the technology transfer between advanced and third world countries is presented. The role of cooperation agreements between developing countries is also discussed. (M.C.K.)

  5. Intense ion beam applications to magnetic confinement fusion

    International Nuclear Information System (INIS)

    The ion ring project objective is to trap a ring of high energy, axis-encircling ions in a magnetic mirror. The number of ring ions should be such as to produce deltaB/B on the ring axis of order 10%. The second experiment, LONGSHOT, is directed to producing a long pulse ion beam source so that the total number of protons required for an ion ring can be provided a lower diode power and, hence, at much less cost than that of 100 nsec pulsed power generators like the NRL GAMBLE II. A detailed report of the progress on IREX and LONGSHOT is given

  6. Relevance of advanced nuclear fusion research: Breakthroughs and obstructions

    Science.gov (United States)

    Coppi, Bruno

    2016-03-01

    An in depth understanding of the collective modes that can be excited in a wide range of high-energy plasmas is necessary to advance nuclear fusion research in parallel with other fields that include space and astrophysics in particular. Important achievements are shown to have resulted from implementing programs based on this reality, maintaining a tight connection with different areas of investigations. This involves the undertaking of a plurality of experimental approaches aimed at understanding the physics of fusion burning plasmas. At present, the most advanced among these is the Ignitor experiment involving international cooperation, that is designed to investigate burning plasma regimes near ignition for the first time.

  7. Remote operations in a Fusion Engineering Research Facility (FERF)

    International Nuclear Information System (INIS)

    The proposed Fusion Engineering Research Facility (FERF) has been designed for the test and evaluation of materials that will be exposed to the hostile radiation environment created by fusion reactors. Because the FERF itself must create a very hostile radiation environment, extensive remote handling procedures will be required as part of its routine operations as well as for both scheduled and unscheduled maintenance. This report analyzes the remote-handling implications of a vertical- rather than horizontal-orientation of the FERF magnet, describes the specific remote-handling facilities of the proposed FERF installation and compares the FERF remote-handling system with several other existing and proposed facilities. (U.S.)

  8. Future directions of magnetic fusion research

    International Nuclear Information System (INIS)

    The results from the worldwide research on tokamaks together with the engineering design of the International Thermonuclear Experimental Reactor (ITER) and power plant systems studies have identified opportunities and challenges not only for the tokamak concept but for most toroidal magnetic confinement concepts. Though the tokamak configuration has been the most intensely studied to date, other magnetic configurations have been pursued to identify their potential as power plants. The experimental results from a variety of magnetic configurations together with theoretical work has deepened our understanding and has provided insights into the directions future research will take to develop an economically attractive energy source. (author). 76 refs

  9. Fusion Reactor Safety Research Program annual report, FY-79

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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 (e.g., magnet systems, superconducting materials development, environmental and safety studies, advanced gyrotron development for RF heating, preconceptual design studies of torsatrons and stellarators, and advanced tokamak design and reactor studies).

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

    International Nuclear Information System (INIS)

    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

  12. EU socio-economic research on fusion: findings and program

    International Nuclear Information System (INIS)

    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)

  13. EU socio-economic research on fusion: Findings and program

    International Nuclear Information System (INIS)

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

  14. Accelerator and Fusion Research Division: 1987 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1988-04-01

    An overview of the design and the initial studies for the Advanced Light Source is given. The research efforts for the Center for X-Ray Optics include x-ray imaging, multilayer mirror technology, x-ray sources and detectors, spectroscopy and scattering, and synchrotron radiation projects. The Accelerator Operations highlights include the research by users in nuclear physics, biology and medicine. The upgrade of the Bevalac is also discussed. The High Energy Physics Technology review includes the development of superconducting magnets and superconducting cables. A review of the Heavy-Ion Fusion Accelerator Research is also presented. The Magnetic Fusion Energy research included the development of ion sources, accelerators for negative ions, diagnostics, and theoretical plasma physics. (WRF)

  15. Accelerator and Fusion Research Division: 1987 summary of activities

    International Nuclear Information System (INIS)

    An overview of the design and the initial studies for the Advanced Light Source is given. The research efforts for the Center for X-Ray Optics include x-ray imaging, multilayer mirror technology, x-ray sources and detectors, spectroscopy and scattering, and synchrotron radiation projects. The Accelerator Operations highlights include the research by users in nuclear physics, biology and medicine. The upgrade of the Bevalac is also discussed. The High Energy Physics Technology review includes the development of superconducting magnets and superconducting cables. A review of the Heavy-Ion Fusion Accelerator Research is also presented. The Magnetic Fusion Energy research included the development of ion sources, accelerators for negative ions, diagnostics, and theoretical plasma physics

  16. Applications of Fusion Energy Sciences Research - Scientific Discoveries and New Technologies Beyond Fusion

    Energy Technology Data Exchange (ETDEWEB)

    Wendt, Amy [Univ. of Wisconsin, Madison, WI (United States); Callis, Richard [General Atomics, San Diego, CA (United States); Efthimion, Philip [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Foster, John [Univ. of Michigan, Ann Arbor, MI (United States); Keane, Christopher [Washington State Univ., Pullman, WA (United States); Onsager, Terry [National Oceanic and Atmospheric Administration (NOAA), Boulder, CO (United States); O' Shea, Patrick [Univ. of Maryland, College Park, MD (United States)

    2015-09-01

    Since the 1950s, scientists and engineers in the U.S. and around the world have worked hard to make an elusive goal to be achieved on Earth: harnessing the reaction that fuels the stars, namely fusion. Practical fusion would be a source of energy that is unlimited, safe, environmentally benign, available to all nations and not dependent on climate or the whims of the weather. Significant resources, most notably from the U.S. Department of Energy (DOE) Office of Fusion Energy Sciences (FES), have been devoted to pursuing that dream, and significant progress is being made in turning it into a reality. However, that is only part of the story. The process of creating a fusion-based energy supply on Earth has led to technological and scientific achievements of far-reaching impact that touch every aspect of our lives. Those largely unanticipated advances, spanning a wide variety of fields in science and technology, are the focus of this report. There are many synergies between research in plasma physics, (the study of charged particles and fluids interacting with self-consistent electric and magnetic fields), high-energy physics, and condensed matter physics dating back many decades. For instance, the formulation of a mathematical theory of solitons, solitary waves which are seen in everything from plasmas to water waves to Bose-Einstein Condensates, has led to an equal span of applications, including the fields of optics, fluid mechanics and biophysics. Another example, the development of a precise criterion for transition to chaos in Hamiltonian systems, has offered insights into a range of phenomena including planetary orbits, two-person games and changes in the weather. Seven distinct areas of fusion energy sciences were identified and reviewed which have had a recent impact on fields of science, technology and engineering not directly associated with fusion energy: Basic plasma science; Low temperature plasmas; Space and astrophysical plasmas; High energy density

  17. The Swedish fusion research programme on magnetic confinement 1978

    International Nuclear Information System (INIS)

    A review is given on the activities and plans for research on plasma physics and controlled fusion at the Royal Institute of Technology in Stockholm, with descriptions and motivations of the research lines being conducted. These activities include investigations on plasma-neutral gas interaction, development of special principles for plasma stabilization, magnetic confinement schemes being based mainly on poloidal fields, as well as the generation, heating, and diagnostics of plasmas being ''impermeable'' to neutral gas. (author)

  18. Inertial fusion research. Annual technical report, 1984

    International Nuclear Information System (INIS)

    This report contains research progress during this period on each of the following 5 areas: (1) parametric instabilities, (2) cryogenic implosion experiments, (3) x-ray laser experiments, (4) XCALIBR, an effective soft x-ray calibration facility, and (5) DELPHI- a new hydrodynamics code, (6) polymer technology, (7) glass shell technology, (8) shell production facility, (9) cryogenic technology, (10) characterization and quality assurance, and (11) coating technology

  19. Inertial fusion energy target injection, tracking, and beam pointing

    Energy Technology Data Exchange (ETDEWEB)

    Petzoldt, R.W.

    1995-03-07

    Several cryogenic targets must be injected each second into a reaction chamber. Required target speed is about 100 m/s. Required accuracy of the driver beams on target is a few hundred micrometers. Fuel strength is calculated to allow acceleration in excess of 10,000 m/s{sup 2} if the fuel temperature is less than 17 K. A 0.1 {mu}m thick dual membrane will allow nearly 2,000 m/s{sup 2} acceleration. Acceleration is gradually increased and decreased over a few membrane oscillation periods (a few ms), to avoid added stress from vibrations which could otherwise cause a factor of two decrease in allowed acceleration. Movable shielding allows multiple targets to be in flight toward the reaction chamber at once while minimizing neutron heating of subsequent targets. The use of multiple injectors is recommended for redundancy which increases availability and allows a higher pulse rate. Gas gun, rail gun, induction accelerator, and electrostatic accelerator target injection devices are studied, and compared. A gas gun is the preferred device for indirect-drive targets due to its simplicity and proven reliability. With the gas gun, the amount of gas required for each target (about 10 to 100 mg) is acceptable. A revolver loading mechanism is recommended with a cam operated poppet valve to control the gas flow. Cutting vents near the muzzle of the gas gun barrel is recommended to improve accuracy and aid gas pumping. If a railgun is used, we recommend an externally applied magnetic field to reduce required current by an order of magnitude. Optical target tracking is recommended. Up/down counters are suggested to predict target arrival time. Target steering is shown to be feasible and would avoid the need to actively point the beams. Calculations show that induced tumble from electrostatically steering the target is not excessive.

  20. Inertial fusion energy target injection, tracking, and beam pointing

    International Nuclear Information System (INIS)

    Several cryogenic targets must be injected each second into a reaction chamber. Required target speed is about 100 m/s. Required accuracy of the driver beams on target is a few hundred micrometers. Fuel strength is calculated to allow acceleration in excess of 10,000 m/s2 if the fuel temperature is less than 17 K. A 0.1 μm thick dual membrane will allow nearly 2,000 m/s2 acceleration. Acceleration is gradually increased and decreased over a few membrane oscillation periods (a few ms), to avoid added stress from vibrations which could otherwise cause a factor of two decrease in allowed acceleration. Movable shielding allows multiple targets to be in flight toward the reaction chamber at once while minimizing neutron heating of subsequent targets. The use of multiple injectors is recommended for redundancy which increases availability and allows a higher pulse rate. Gas gun, rail gun, induction accelerator, and electrostatic accelerator target injection devices are studied, and compared. A gas gun is the preferred device for indirect-drive targets due to its simplicity and proven reliability. With the gas gun, the amount of gas required for each target (about 10 to 100 mg) is acceptable. A revolver loading mechanism is recommended with a cam operated poppet valve to control the gas flow. Cutting vents near the muzzle of the gas gun barrel is recommended to improve accuracy and aid gas pumping. If a railgun is used, we recommend an externally applied magnetic field to reduce required current by an order of magnitude. Optical target tracking is recommended. Up/down counters are suggested to predict target arrival time. Target steering is shown to be feasible and would avoid the need to actively point the beams. Calculations show that induced tumble from electrostatically steering the target is not excessive

  1. Impact of beam transport method on chamber and driver design for heavy ion inertial fusion energy

    Energy Technology Data Exchange (ETDEWEB)

    Rose, D.V.; Welch, D.R.; Olson, C.L.; Yu, S.S.; Neff, S.; Sharp, W.M.

    2002-12-01

    In heavy ion inertial fusion energy systems, intense beams of ions must be transported from the exit of the final focus magnet system through the target chamber to hit millimeter spot sizes on the target. In this paper, we examine three different modes of beam propagation: neutralized ballistic transport, assisted pinched transport, and self-pinched transport. The status of our understanding of these three modes is summarized, and the constraints imposed by beam propagation upon the chamber environment, as well as their compatibility with various chamber and target concepts, are considered. We conclude that, on the basis of our present understanding, there is a reasonable range of parameter space where beams can propagate in thick-liquid wall, wetted-wall, and dry-wall chambers.

  2. Beam combined laser fusion driver using stimulated Brillouin scattering phase conjugation mirrors

    International Nuclear Information System (INIS)

    The beam combination method using stimulated Brillouin scattering phase conjugate mirrors (SBS-PCMs) is a promising technique for realizing the laser fusion driver with an ultrahigh energy/power laser system operating with a high repetition rate over 10 Hz. For realizing the beam combined laser system, it is necessary to lock/control the phases of SBS beams. In our previous papers, the new phase control technique using the self-generated density modulation was proposed, and its principle has been demonstrated experimentally. However, all the previous works were done without amplifiers. In this work, it has been demonstrated that the phase is stabilized with λ /51 fluctuation by standard deviation during 5,000 laser shots (500 sec.) in the two-beam combination system with amplifiers with 200 mJ total output energy and 10 Hz repletion rate. (author)

  3. General design of the International Fusion Materials Irradiation Facility deuteron injector: Source and beam line

    International Nuclear Information System (INIS)

    In the framework of the International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities (IFMIF-EVEDA) project, CEA/IRFU is in charge of the design and realization of the 140 mA cw deuteron Injector. The electron cyclotron resonance ion source operates at 2.45 GHz and a 4 electrode extraction system has been chosen. A 2 solenoid beam line, together with a high space charge compensation have been optimized for a proper beam injection in the 175 MHz radio frequency quadrupole. The injector will be tested with proton and deuteron beam production either in pulsed mode or in cw mode on the CEA-Saclay site before to be shipped to Japan. Special attention was paid to neutron emission due to (d,D) reaction. In this paper, the general IFMIF Injector design is reported, pointing out beam dynamics, radioprotection, diagnostics, and mechanical aspects.

  4. Atomic data for controlled fusion research

    International Nuclear Information System (INIS)

    Presented is an evaluated graphical and tabular compilation of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are tabulated and graphed as a function of energy for collision processes involving heavy particles, electrons, and photons with atoms and ions. Also included are sections on data for particle penetration through macroscopic matter, particle transport properties, particle interactions with surfaces, and pertinent charged particle nuclear cross sections and reaction rates. In most cases estimates have been made of the data accuracy

  5. Electromagnetic waves for thermonuclear fusion research

    CERN Document Server

    Mazzucato, Ernesto

    2014-01-01

    The science of magnetically confined plasmas covers the entire spectrum of physics from classical and relativistic electrodynamics to quantum mechanics. During the last sixty years of research, our initial primitive understanding of plasma physics has made impressive progress thanks to a variety of experiments - from tabletop devices with plasma temperatures of a few thousands of degrees and confinement times of less than 100 microseconds, to large tokamaks with plasma temperatures of up to five hundred million degrees and confinement times approaching one second. We discovered that plasma con

  6. Status of cold fusion research in Japan

    International Nuclear Information System (INIS)

    In Japan, the Condensed Matter Nuclear Science (CMNS) works have been centering around the Japan CF-Research Society (JCFRS) established in 1999. Recently, about 10 research groups were actively working in the CMNS field, and have been exchanging information mainly in the annual meetings of JCFRS in addition to the International ICCF conferences. For many years efforts have been exclusively devoted to clarification of the underlying physics of excess heat phenomenon and isotopic composition change. Recently, however, an entrepreneur group, Clean Planet Inc., has entered into the CMNS field in Japan, and joined Mizuno to form the above-mentioned group and made a presentation at the LANR/CF Colloquium, at MIT in March 2014. In their work they used glow discharge to form surface nanostructures on nickel mesh wires that are to be subjected to deuterium exposure. They claimed excess power on the order of kilowatts with a coefficient of performance of 1.9. Confirmation of their claim by third parties is highly expected

  7. Beam illumination and implosion simulation in inertial confinement heavy ion fusion

    International Nuclear Information System (INIS)

    Three-dimensional computer simulations are performed for a heavy ion beam (HIB) irradiation onto a direct-driven spherical fuel pellet in heavy ion fusion (HIF). In addition, the non-uniformity growth due to a little pellet displacement from a reactor chamber center is investigated. The calculation results demonstrate that we can realize a rather low non-uniform energy deposition: for example, less than 2.0% even for a 32-beam irradiation system. Moreover we develop hydrodynamic simulation code to calculate a target implosion. (author)

  8. 3d and r,z particle simulations of Heavy Ion Fusion beams

    International Nuclear Information System (INIS)

    The space-charge-dominated beams in a Heavy Ion beam driven inertial Fusion (HIF) accelerator must be focuses onto small (few mm) spots at the fusion target, and so preservation of a small emittance is crucial. The nonlinear beam self-fields can lead to emittance growth; thus, a self-consistent field description is necessary. We have developed a multi-dimensional time-dependent discrete particle simulation code, WARP, and are using it to study the behavior of HIF beams. The code's 3d package combines features of an accelerator code and a particle-in-cell (PIC) plasma simulation. Novel techniques allow it to follow beams through many accelerator elements over long distances and around bends. We have used the code to understand the emittance growth observed in the MBE4 experiment at. Lawrence Berkeley Laboratory (LBL) under conditions of aggressive drift-compression. We are currently applying it to LBL's planned ILSE experiments, and (most recently) to an ESQ injector option being evaluated for ILSE. The code's r, z package is being used to study the axial confinement afforded by the shaped ends of the accelerating pulses, and to study longitudinal instability induced by induction module impedance

  9. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    International Nuclear Information System (INIS)

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios

  10. Present status of liquid metal research for a fusion reactor

    Science.gov (United States)

    Tabarés, Francisco L.

    2016-01-01

    Although the use of solid materials as targets of divertor plasmas in magnetic fusion research is accepted as the standard solution for the very challenging issue of power and particle handling in a fusion reactor, a generalized feeling that the present options chosen for ITER will not represent the best choice for a reactor is growing up. The problems found for tungsten, the present selection for the divertor target of ITER, in laboratory tests and in hot plasma fusion devices suggest so. Even in the absence of the strong neutron irradiation expected in a reactor, issues like surface melting, droplet ejection, surface cracking, dust generation, etc., call for alternative solutions in a long pulse, high efficient fusion energy-producing continuous machine. Fortunately enough, decades of research on plasma facing materials based on liquid metals (LMs) have produced a wealth of appealing ideas that could find practical application in the route to the realization of a commercial fusion power plant. The options presently available, although in a different degree of maturity, range from full coverage of the inner wall of the device with liquid metals, so that power and particle exhaust together with neutron shielding could be provided, to more conservative combinations of liquid metal films and conventional solid targets basically representing a sort of high performance, evaporative coating for the alleviation of the surface degradation issues found so far. In this work, an updated review of worldwide activities on LM research is presented, together with some open issues still remaining and some proposals based on simple physical considerations leading to the optimization of the most conservative alternatives.

  11. 1978 annual report on laser fusion research

    International Nuclear Information System (INIS)

    Progress during this period is reported for each of the following topics: (1) spherical shell fuel containers, (2) polymer research, (3) cryogenic technology, (4) fabrication technology, (5) implosion physics, (6) fast ion measurements of laser-produced spherical plasmas, (7) absorbed energy measurements, (8) diagnostics, (9) fast ion energy loss in dense plasmas, (10) electron transport, (11) ionization equation of state, (12) profile modification by pondermotive forces, (13) pondermotive potential effects on Ohm's law, (14) effect of flux-limited thermal transport on critical surface jump conditions, (15) spherical rarefaction shocks, (16) explosively heated Gaussian objects, (17) bandwidth broadening, (18) frequency doubling experiments, (19) advanced laser candidates, (20) glass laser operation, and (21) 2TW laser upgrade

  12. 1978 annual report on laser fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, R.R. (ed.)

    1978-01-01

    Progress during this period is reported for each of the following topics: (1) spherical shell fuel containers, (2) polymer research, (3) cryogenic technology, (4) fabrication technology, (5) implosion physics, (6) fast ion measurements of laser-produced spherical plasmas, (7) absorbed energy measurements, (8) diagnostics, (9) fast ion energy loss in dense plasmas, (10) electron transport, (11) ionization equation of state, (12) profile modification by pondermotive forces, (13) pondermotive potential effects on Ohm's law, (14) effect of flux-limited thermal transport on critical surface jump conditions, (15) spherical rarefaction shocks, (16) explosively heated Gaussian objects, (17) bandwidth broadening, (18) frequency doubling experiments, (19) advanced laser candidates, (20) glass laser operation, and (21) 2TW laser upgrade. (MOW)

  13. Characterization of the Plasma Edge for Technique of Atomic Helium Beam in the CIEMAT Fusion Device

    International Nuclear Information System (INIS)

    In this report, the measurement of Electron Temperature and Density in the Boundary Plasma of TJ-II with a Supersonic Helium Beam Diagnostic and work devoted to the upgrading of this technique are described. Also, simulations of Laser Induced Fluorescence (LIF) studies of level populations of electronically excited He atoms are shown. This last technique is now being installed in the CIEMAT fusion device. (Author )

  14. Heat transfer phenomena in gas protected particle beam fusion reactor cavities

    International Nuclear Information System (INIS)

    The behavior of the fireball produced in particle beam fusion reactor cavities as the cavity gas near the target absorbs the X-rays and ionic debris emanating from the microexplosion is examined. Thermal response of the first wall to the radiative heat flux from the gas is examined parametrically. Criteria for the suitability of different cavity fill gases based on their ability to protect the first wall from excessive surface heating and ablation are discussed. 9 refs

  15. Research on Brightness Measurement of Intense Electron Beam

    CERN Document Server

    Wang, Yuan; Zhang, Huang; Yang, GuoJun; Li, YiDing; Li, Jin

    2015-01-01

    The mostly research fasten on high emission density of injector to study electron beam's brightness in LIA. Using the injector(2MeV) was built to research brightness of multi-pulsed high current(KA) electron beam, and researchs three measurement method (the pepper-pot method, beam collimator without magnetic field, beam collimator with magnetic field method) to detect beam's brightness with time-resolved measurement system.

  16. Fusion reactivity, confinement, and stability of neutral-beam heated plasmas in TFTR and other tokamaks

    International Nuclear Information System (INIS)

    The hypothesis that the heating beam fueling profile shape connects the edge condition and improved core confinement and fusion reactivity is extensively studied on TFTR and applied to other tokamaks. The derived absolute scalings based on beam fueling profile shape for the stored energy and neutron yield can be applied to the deuterium discharges at different major radii in TFTR. These include Supershot, High poloidal beta, L-mode, and discharges with a reversed shear (RS) magnetic configuration. These scalings are also applied to deuterium-tritium discharges. The role of plasma parameters, such as plasma current, Isdo2(p), edge safety factor, qsdo5(a), and toroidal field, Bsdo2(T), in the performance and stability of the discharges is explicitly studied. Based on practical and externally controllable plasma parameters, the limitation and optimization of fusion power production of the present TFTR is investigated and a path for a discharge condition with fusion power gain, Q > 1 is suggested based on this study. Similar physics interpretation is provided for beam heated discharges on other major tokamaks

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

    International Nuclear Information System (INIS)

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

  18. Maryland magnetic fusion research program: MS speromak

    International Nuclear Information System (INIS)

    The main theme of our present experimentation on MS is to prolong the spheromak lifetime. This research has been concerned with such topics as passive MHD stabilization coils, impurity control and increased energy storage. At the present time the longest lived plasmas appear to be line tied to the liner or reversal coils. The natural consequence of having net flux outside the separatrix and a resistive plasma is that the plasma shrinks in time. At some point in time the plasma is far enough from the liner, or stabilization coils, that it becomes unstable. If we increase the bias field so as to move the separatrix further inside the liner, the plasma becomes unstable earlier as the separatrix moves to a smaller radius in a shorter time than if it starts out outside the liner. We have tried to circumvent this behavior with various configurations of passive conductors used as stabilizing elements. In this paper, we detail some of the machine modifications that have been tried in attempts to produce a stable, long-lived plasma

  19. U.S. heavy ion beam science towards inertial fusion energy

    International Nuclear Information System (INIS)

    Significant experimental and theoretical progress in the U.S heavy-ion fusion (HIF) program is reported in modeling and measurements of intense space-charge-dominated heavy ion and electron beams. Measurements of the transport of a well-matched and aligned high current (0.2A) 1.0 MeV potassium ion beam through 10 electric quadrupoles, with a fill factor of 60%, shows no emittance growth within experimental measurement uncertainty, as expected from the simulations. Another experiment shows that passing a beam through an aperture can reduce emittance to near the theoretical limits, and that plasma neutralization of the beam's space-charge can greatly reduce the focal spot radius. Measurements of intense beamlet current density, emittance, charge-state purity, and energy spread from a new, high-brightness, Argon plasma source for HIF experiments are described. New theory and simulations of neutralization of intense beam space charge with plasma in various focusing chamber configurations indicate that near-emittance-limited beam focal spot sizes can be obtained even with beam perveance an order of magnitude higher than in earlier HIF focusing experiments. (author)

  20. Modeling of direct beam extraction for a high-charge-state fusion driver

    Science.gov (United States)

    Anderson, O. A.; Grant Logan, B.

    A newly proposed type of multicharged ion source offers the possibility of an economically advantageous high-charge-state fusion driver. Multiphoton absorption in an intense uniform laser focus can give multiple charge states of high purity, simplifying or eliminating the need for charge-state separation downstream. Very large currents (hundreds of amperes) can be extracted from this type of source. Several arrangements are possible. For example, the laser plasma could be tailored for storage in a magnetic bucket, with beam extracted from the bucket. A different approach, described in this report, is direct beam extraction from the expanding laser plasma. We discuss extraction and focusing for the particular case of a 4.1 MV beam of Xe 16+ ions. The maximum duration of the beam pulse is limited by the total charge in the plasma, while the practical pulse length is determined by the range of plasma radii over which good beam optics can be achieved. The extraction electrode contains a solenoid for beam focusing. Our design studies were carried out first with an envelope code and then with a self-consistent particle code. Results from our initial model showed that hundreds of amperes could be extracted, but that most of this current missed the solenoid entrance or was intercepted by the wall and that only a few amperes were able to pass through. We conclude with an improved design which increases the surviving beam to more than 70 A.

  1. Computing for magnetic fusion energy research: An updated vision

    International Nuclear Information System (INIS)

    This Fusion Computing Council perspective is written to present the primary of the fusion computing community at the time of publication of the report necessarily as a summary of the information contained in the individual sections. These concerns reflect FCC discussions during final review of contributions from the various working groups and portray our latest information. This report itself should be considered as dynamic, requiring periodic updating in an attempt to track rapid evolution of the computer industry relevant to requirements for magnetic fusion research. The most significant common concern among the Fusion Computing Council working groups is networking capability. All groups see an increasing need for network services due to the use of workstations, distributed computing environments, increased use of graphic services, X-window usage, remote experimental collaborations, remote data access for specific projects and other collaborations. Other areas of concern include support for workstations, enhanced infrastructure to support collaborations, the User Service Centers, NERSC and future massively parallel computers, and FCC sponsored workshops

  2. The preliminary research for biosynthetic engineering by radiation fusion technology

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Chang Hyun; Jung, U Hee; Park, Hae Ran [KAERI, Daejeon (Korea, Republic of)

    2012-01-15

    The purpose of this project is to elucidate the solution to the production of bioactive substance using biotransformation process from core technology of biosynthetic engineering by radiation fusion technology. And, this strategy will provide core technology for development of drugs as new concept and category. Research scopes and contents of project include 1) The development of mutant for biosynthetic engineering by radiation fusion technology 2) The development of host for biosynthetic engineering by radiation fusion technology 3) The preliminary study for biosynthetic engineering of isoflavone by radiation fusion technology. The results are as follows. Isoflavone compounds(daidzein, hydroxylated isoflavone) were analyzed by GC-MS. The study of radiation doses and p-NCA high-throughput screening for mutant development were elucidated. And, it was carried out the study of radiation doses for host development. Furthermore, the study of redox partner and construction of recombinant strain for region-specific hydroxylation(P450, redox partner). In addition, the biological effect of 6,7,4'-trihydroxyisoflavone as an anti-obesity agent was elucidated in this study.

  3. Plasma physics and controlled nuclear fusion research 1990. V. 1

    International Nuclear Information System (INIS)

    Volume 1 of the Proceedings of the Thirteenth International Conference on Plasma Physics and Controlled Nuclear Fusion Research contains papers given in two of the sessions: A and E. Session A contains the Artsimovich Memorial Lecture and papers on tokamaks; session E papers on plasma heating and current drive. The titles and authors of each paper are listed in the Contents. Abstracts accompany each paper. Refs, figs and tabs

  4. High peak power Nd:glass lasers for fusion research

    International Nuclear Information System (INIS)

    This paper briefly reviews the basics of fusion and some of the major problems associated with building a 4 arms 1 kJ, 1 ns Nd:glass laser chain currently under development at the Bhabha Atomic Research Centre(BARC), Bombay. With this laser, it is proposed to study the various laser plasma interaction processes and to obtain compression of glass micro balloon targets filled with DT gas. (author). 15 refs., 8 figs., 3 tabs

  5. FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

    Energy Technology Data Exchange (ETDEWEB)

    Karttunen, S.; Heikkinen, J.; Korhonen, R. [VTT Energy, Espoo (Finland)] [and others

    1998-12-31

    This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

  6. FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

    International Nuclear Information System (INIS)

    This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

  7. Report on the 7th European conference on plasma physics and fusion research

    International Nuclear Information System (INIS)

    This conference dealt mainly with Tokamak experiments, laser fusion, effects of impurities, high-frequency heating, cusp geometry and mirror machines. Reports are given on meetings of the International Fusion Research Council, Plasma Physics Board, Euratom Committee of Directors, and the editorial board of 'Nuclear Fusion'. There are 2 appendices in English: 1. A paper on the quasi-steady state of permeable plasmas. 2. The Swedish Fusion Research Programme 1975, with detailed list of lines of research. (J.S.)

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

    International Nuclear Information System (INIS)

    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

  9. Multisensor fusion using the sensor algorithm research expert system

    Science.gov (United States)

    Bullock, Michael E.; Miltonberger, Thomas W.; Reinholdsten, Paul A.; Wilson, Kathleen

    1991-08-01

    A method for object recognition using a multisensor model-based approach has been developed. The sensor algorithm research expert system (SARES) is a sun-based workstation for model-based object recognition algorithm development. SARES is a means to perform research into multiple levels of geometric and scattering models, image and signal feature extraction, hypothesis management, and matching strategies. SARES multisensor fusion allows for multiple geometric representations and decompositions, and sensor location transformations, as well as feature prediction, matching, and evidence accrual. It is shown that the fusion algorithm can exploit the synergistic information contained in IR and synthetic aperture radar (SAR) imagery yielding increased object recognition accuracy and confidence over single sensor exploitation alone. The fusion algorithm has the added benefit of reducing the number of computations by virtue of simplified object model combinatorics. That is, the additional sensor information eliminates a large number of the incorrect object hypotheses early in the algorithm. This provides a focus of attention to those object hypotheses which are closest to the correct hypothesis.

  10. Thermal cycling of cast iron surface by electron beam fusion treatment

    International Nuclear Information System (INIS)

    The technology of cast iron surface hardening, by electron beam fusion treatment, to increase the hardness and wear resistance is very well known. This method causes the great difference of hardness between a surface layer and a base material which creates the sharp structural notch. So, an attempt was made to smooth the structural notch to improve the fusion zone properties. It was decided to use here a carbon diffusion phenomenon against the temperature gradient inside the eutectic cell of ferritic cast iron with nodular graphite. To achieve the temperature gradient, the electron beam as a quasi-linear heat source was used. Owing to a very high power density of heat source and a very short interaction time, the requested temperature gradient inside the eutectic cell was obtained (at great difference of graphite and ferrite thermal properties). As a result of such treatment, a zone of pearlitic structure around the graphite as well as beneath a ledeburitic-martensitic fusion layer was attained. Hence, the significant smoothing of structural notch was obtained. (author)

  11. Energy enhancement for deuteron beam fast ignition of a precompressed inertial confinement fusion target

    International Nuclear Information System (INIS)

    Fast Ignition (FI) is recognized as a potentially promising approach to achieve the high-energy-gain target performance needed for commercial inertial confinement fusion. Here we consider deuteron beam driven FI which provides not only the 'hot spot' ignition spark, but also extra ''bonus'' fusion energy through reactions in the target. In this study, we estimate the impact of the added deposition energy due to the fusion reactions occurring, based on calculations using a modified energy multiplication factor Fc. The deuteron beam energy deposition range and time are also evaluated in order to estimate the desired deuteron initial energy. It is shown that an average of 30% extra energy can be gained from deuterons with 1 MeV initial energy and 12% from deuterons with 3 MeV initial energy. These results indicate that the energy benefit of this approach could be significant, but a much more comprehensive calculation is needed to realize a full 3D design for realistic experimental studies.

  12. EURATOM/UKAEA Association fusion research. 2002/2003 progress report

    International Nuclear Information System (INIS)

    This is a report on work carried out between April 2002 to March 2003 by the EURATOM/UKAEA Fusion Association, mainly at the Culham Science Centre in Oxfordshire, UK, in support of the European research programme into energy production from controlled fusion. This could in principle provide effectively limitless electricity, with security of supply, inherent safety, and minimal environmental impact. At the end of March 2003 funding of fusion research in the UK was transferred from the Office of Science and Technology at the Department of Trade and Industry to the Engineering and Physical Sciences Research Council. A Fusion Advisory Board has also been established, to provide external guidance and monitoring of the programme. Fusion research in Europe is based primarily on the tokamak concept, in which the fuel, an ionised gas ('plasma'), is confined by a magnetic field produced by currents in external coils and in the fuel itself. The Joint European Torus (JET) tokamak at Culham is Europe's principal fusion experiment, and one of the two leading devices of its type in the world. Both the UK programme and the European programme as a whole are increasingly focussed on ITER, a proposed tokamak that would test the plasma performance and most of the technology required for a fusion power plant. Negotiations on the siting and construction of ITER, boosted by the accession of the USA, China and, most recently, South Korea, are progressing towards a conclusion in 2004. The EURATOM/UKAEA Association operates the JET facilities for visiting scientists from all the EURATOM Fusion Associations. Several improvements to JET were implemented by UKAEA in 2002/03, including improved neutral beam injectors and an additional pellet injection track. UKAEA has also contributed to the scientific and technical programme on JET, notably in studies of energy confinement in the baseline 'ELMy H-mode' operating regime envisaged for ITER, the formation of internal transport barriers in

  13. Annual report of Naka Fusion Research Establishment from April 1, 2003 to March 31, 2004

    International Nuclear Information System (INIS)

    This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2003 to 31 March, 2004. The activities in the Naka Fusion Research Establishment are highlighted by researches in JT-60 and JFT-2M, theoretical and analytical plasma researches, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction. (J.P.N.)

  14. HIBALL - a conceptual heavy ion beam driven fusion reactor study. Vol. 2

    International Nuclear Information System (INIS)

    A preliminary concept for a heavy-ion beam driven inertial confinement fusion power plant is presented. The high repetition rate of the RF accelerator driver is utilized to serve four reactor chambers alternatingly. In the chambers a novel first-wall protection scheme is used. At a target gain of 83 the total net electrical output is 3.8 GW. The recirculating power fraction is below 15%. The main goal of the comprehensive HIBALL study (which is continuing) is to demonstrate the compatibility of the design of the driver, the target and the reactor chambers. Though preliminary, the present design is essentially self-consistent. Tentative cost estimates are given. The costs compare well with those found in similar studies on other types of fusion reactors. (orig.)

  15. HIBALL - a conceptual heavy ion beam driven fusion reactor study. Vol. 1

    International Nuclear Information System (INIS)

    A preliminary concept for a heavy-ion beam driven inertial confinement fusion power plant is presented. The high repetition rate of the RF accelerator driver is utilized to serve four reactor chambers alternatingly. In the chambers a novel first-wall protection scheme is used. At a target gain of 83 the total net electrical output is 3.8 GW. The recirculating power fraction is below 15%. The main goal of the comprehensive HIBALL study (which is continuing) is to demonstrate the compatibility of the design of the driver, the target and the reactor chambers. Though preliminary, the present dessign is essentially self-consistent. Tentative cost estimates are given. The costs compare well with those found in similar studies on other types of fusion reactors. (orig.)

  16. Dynamical Dipole mode in heavy-ion fusion reactions by using stable and radioactive beams

    International Nuclear Information System (INIS)

    The existence of the dynamical dipole mode in the 192Pb composite system was investigated through the study of its prompt decay employing the 40Ca + 152Sm and 48Ca + 144Sm reactions at E(lab)=11 and 10.1 MeV/u, respectively. The γ-rays and light charged particles were detected in coincidence with evaporation residues and fission fragments. First results of this experiment show that the dynamical dipole mode survives in collisions involving heavier mass reaction partners than those studied previously. As a fast cooling mechanism on the fusion path, the prompt dipole radiation could be of interest for the synthesis of super-heavy elements through 'hot' fusion reactions. Furthermore, by using radioactive beams and the prompt radiation as a probe we could get information on the symmetry energy at sub-saturation densities. (authors)

  17. Copper-coated laser-fusion targets using molecular-beam levitation

    International Nuclear Information System (INIS)

    A series of diagnostic experiments at the Shiva laser fusion facility required targets of glass microspheres coated with 1.5 to 3.0 μm of copper. Previous batch coating efforts using vibration techniques gave poor results due to microsphere sticking and vacuum welding. Molecular Beam Levitation (MBL) represented a noncontact method to produce a sputtered copper coating on a single glassmicrosphere. The coating specifications that were achieved resulted in a copper layer up to 3 μm thick with the allowance of a maximum variation of 10 nm in surface finish and thickness. These techniques developed with the MBL may be applied to sputter coat many soft metals for fusion target applications

  18. Past, present and future of laser fusion research

    International Nuclear Information System (INIS)

    The concept of laser fusion was devised very shortly after the invention of laser. In 1972, the Institute of Laser Engineering, Osaka University was established by the author in accordance with the Edward Teller close-quote s special lecture on open-quote open-quote New Internal Combustion Engine close-quote close-quote for IQEC at Montreal which predicted the implosion fusion. In 1975 we invented the so called indirect drive fusion concept open-quote open-quote Cannonball Target close-quote close-quote which became later to be recognize as a same concept of open-quote open-quote Hohlraum Target close-quote close-quote from Livermore. As well known, ICF research in the US had been veiled for a long time due to the defense classification. While researchers from Japan, Germany and elsewhere have concentrated the efforts to investigate the inertial fusion energy which seems to be very interesting for a future civil energy. They were publishing their own works not only on the direct implosion scheme but also the indirect implosion experiment. These advanced results often frustrated the US researchers who were not allowed to talk about the details of their works. In 1988, international members of the ICF research society including the US scientists gathered together at ECLIM to discuss the necessity of freedom in the ICF research and concluded to make a statement open-quote open-quote Madrid Manifest close-quote close-quote which requested the declassification of the ICF research internationally. After 6 years of halt, the US DOE decided to declassify portions of the program as a part of secretary Hazel O close-quote Leary close-quote s openness initiative. The first revealed presentation from the US was done at Seville 1994, which however were well known already. Classification impeded the progress by restricting the flow of information and did not allow the ICF work to compete by the open scientific security. (Abstract Truncated)

  19. Nonlinear dual-spectral image fusion for improving cone-beam-CT-based breast cancer diagnosis

    Science.gov (United States)

    Chen, Zikuan; Ning, Ruola; Conover, David; Willison, Kathleen

    2006-03-01

    Cone-beam breast computed tomography (CB Breast CT) can easily detect micro-calcifications and distinguish fat and glandular tissues from normal breast tissue. However, it may be a challenging task for CB Breast CT to distinguish benign from malignant tumors because of the subtle difference in x-ray attenuation. Due to the use of polyenergetic x-ray source, the x-ray and tissue interaction exhibits energy-dependent attenuation behavior, a phenomenon that, to date, has not been used for breast tissue characterization. We will exploit this spectral nature by equipping our CB Breast CT with dual-spectral imaging. The dual-spectral cone-beam scanning produces two spectral image datasets, from which we propose a nonlinear dual-spectral image fusion scheme to combine them into a single dataset, thereby incorporating the spectral information. In implementation, we will perform dual-spectral image fusion through a bi-variable polynomial that can be established by applying dual-spectral imaging to a reference material (with eight different thicknesses). From the fused dataset, we can reconstruct a volume, called a reference-equivalent volume or a fusion volume. By selecting the benign tissue as a reference material, we obtain a benign-equivalent volume. Likewise, we obtain a malignant-equivalent volume as well. In the pursuit of the discrimination of benign versus malignant tissues in a breast image, we perform intra-image as well as inter-image processing. The intra-image processing is an intensity transformation imposed only to a tomographic breast image itself, while the inter-image processing is exerted on two tomographic images extracted from two volumes. The nonlinear fusion scheme possesses these properties: 1) no noise magnification; 2) no feature dimensionality problem, and 3) drastic enhancement among specific features offered by nonlinear mapping. Its disadvantage lies in the possible misinterpretation resulting from nonlinear mapping.

  20. Energy demand and possible strategy of fusion research in China

    International Nuclear Information System (INIS)

    Full text: It is predicted by the rapid economic development with 6∼10 % annual increase rate and the population growth that at 2050 the population in China will be 1.5 billion; the total GDP will be 6000-12000 billion US$ and the energy demand will be 5 billion tons of CE and the installed electric capacity will be 1200-1500 GW. So China will face to serious shortage and pollution of energy in near future. The strategy on the development of energy should be at least: 1.The main energy resources in near term will still be the fiscal fuel (coal, gas and oils). The high efficiency and low pollution technologies for using fiscal fuel and the clean and renewable energy resources such as hydrodynamic, solar and wind energy should be strongly supported; 2.The fission power should be developed as more as possible to control the CO2 and other pollutions on atmosphere. In present the nuclear power is only about 1% of total capacity. So the nuclear power demand in China will be extremely huge in next 20 to 40 years. With the rapid and huge development of fission power China will face to new serious problems: 1) strong limitations on the natural uranium ore. So breeding the fission fuel will be very important; 2) how to transmute the huge amount of long-lived radioactive wastes. 3. So China must support fusion energy development as strong as possible from now. The government has given fusion research strong support via EAST, HL-2A and participant of ITER project. The possible strategy for fusion research in China is: 1) The all missions, especially the steady state operation with higher performance plasma on EAST should be achieved under strong support both by CAS and Chinese government within next 10 years; 2) As one of ITER members China should make great effort on the jointed design, construction and assembly of ITER and then on the burning plasma experiments to make the necessary contribution for the future fusion reactor; 3) Basing on the progresses of EAST, ITER and

  1. Research of Multi-sensor Images Based on Color Fusion Methods

    OpenAIRE

    Chunlong Yao; Wei Pan; Lan Shen; Xu Li

    2013-01-01

    With the development of image sensor technology, multi-sensor image fusion technology emerged and was widely used in the field of military surveillance, medical diagnosis, remote sensing, intelligent robot and so on. However, the current image fusion technology mainly focuses on the research of gray images, the color image fusion is rarely. Because color image contains more information compared with gray image, the research on color image fusion technology is becoming more and more urgent. In...

  2. Inertial fusion research at the University of Rochester: progress in direct drive

    International Nuclear Information System (INIS)

    Experiments at the University of Rochester's Laboratory for Laser Energetics (LLE) during the past year with both the 24-beam, 1054-nm OMEGA laser facility and the single-beam, 351-nm GDL system have concentrated on defining the uniformity and the physics of coronal coupling and energy transport in spherical geometry for short-wavelength, direct-drive laser fusion. In this paper, the role of LLE in the United States inertial fusion program is reviewed

  3. Fast ignition of an inertial fusion target with a solid noncryogenic fuel by an ion beam

    Science.gov (United States)

    Gus'kov, S. Yu.; Zmitrenko, N. V.; Il'in, D. V.; Sherman, V. E.

    2015-09-01

    The burning efficiency of a preliminarily compressed inertial confinement fusion (ICF) target with a solid noncryogenic fuel (deuterium-tritium beryllium hydride) upon fast central ignition by a fast ion beam is studied. The main aim of the study was to determine the extent to which the spatial temperature distribution formed under the heating of an ICF target by ion beams with different particle energy spectra affects the thermonuclear gain. The study is based on a complex numerical modeling including computer simulations of (i) the heating of a compressed target with a spatially nonuniform density and temperature distributions by a fast ion beam and (ii) the burning of the target with the initial spatial density distribution formed at the instant of maximum compression of the target and the initial spatial temperature distribution formed as a result of heating of the compressed target by the ion beam. The threshold energy of the igniting ion beam and the dependence of the thermonuclear gain on the energy deposited in the target are determined.

  4. Fast ignition of an inertial fusion target with a solid noncryogenic fuel by an ion beam

    Energy Technology Data Exchange (ETDEWEB)

    Gus’kov, S. Yu., E-mail: guskov@sci.lebedev.ru [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation); Zmitrenko, N. V. [Russian Academy of Sciences, Keldysh Institute of Applied Mathematics (Russian Federation); Il’in, D. V.; Sherman, V. E. [St. Petersburg State Polytechnic University (Russian Federation)

    2015-09-15

    The burning efficiency of a preliminarily compressed inertial confinement fusion (ICF) target with a solid noncryogenic fuel (deuterium-tritium beryllium hydride) upon fast central ignition by a fast ion beam is studied. The main aim of the study was to determine the extent to which the spatial temperature distribution formed under the heating of an ICF target by ion beams with different particle energy spectra affects the thermonuclear gain. The study is based on a complex numerical modeling including computer simulations of (i) the heating of a compressed target with a spatially nonuniform density and temperature distributions by a fast ion beam and (ii) the burning of the target with the initial spatial density distribution formed at the instant of maximum compression of the target and the initial spatial temperature distribution formed as a result of heating of the compressed target by the ion beam. The threshold energy of the igniting ion beam and the dependence of the thermonuclear gain on the energy deposited in the target are determined.

  5. Fast ignition of an inertial fusion target with a solid noncryogenic fuel by an ion beam

    International Nuclear Information System (INIS)

    The burning efficiency of a preliminarily compressed inertial confinement fusion (ICF) target with a solid noncryogenic fuel (deuterium-tritium beryllium hydride) upon fast central ignition by a fast ion beam is studied. The main aim of the study was to determine the extent to which the spatial temperature distribution formed under the heating of an ICF target by ion beams with different particle energy spectra affects the thermonuclear gain. The study is based on a complex numerical modeling including computer simulations of (i) the heating of a compressed target with a spatially nonuniform density and temperature distributions by a fast ion beam and (ii) the burning of the target with the initial spatial density distribution formed at the instant of maximum compression of the target and the initial spatial temperature distribution formed as a result of heating of the compressed target by the ion beam. The threshold energy of the igniting ion beam and the dependence of the thermonuclear gain on the energy deposited in the target are determined

  6. Energy demand and possible strategy of fusion research in China

    International Nuclear Information System (INIS)

    China, presently the country with the world's largest population, will face serious pollution problems and shortage of energy in the near future to face the foreseen rapid social-economic development. Fossil fuels (coal, gas and oils) will be the main energy resources responsible for serious pollution and environmental problems in the long term. The energy development strategy recently declared by the government include: 1) develop the technologies for high efficiency, / low pollution utilization of fossil fuel, especially coal, the development of clean and renewable energy such as hydrodynamic, solar, wind and biomass will be strongly supported; 2) the fission power will be developed as far as possible in next 10 to 40 years. Rapid development of fission power will pose a new and serious problem for China namely, shortage of the natural uranium ore and large amounts of radioactive wastes with long half-lives to deal with; 3) Therefore, China must support fusion energy development as much as possible from now. The possible strategy for fusion research in China is: strengthen the support for EAST to achieve its scientific missions as soon as possible and support ITER activities on the joint design, construction, assembly and burning plasma experiments; to begin the conceptual and engineering design of the test fusion reactor as soon as possible and promote construction of the test reactor due to be constructed around 2020∼2030. Several conceptual designs of test reactors with different blankets have been proposed. It is hoped that the first fusion power plant will be constructed around 2040∼2050. (author)

  7. HIBALL-II - an improved conceptual heavy ion beam driven fusion reactor study

    International Nuclear Information System (INIS)

    An improved design of the HIBALL inertial-confinement fusion power station is presented. The new RF-linac based heavy ion driver has improved concepts for beam stacking, bunching and final focusing. The new target design takes into account radiation transport effects in a coarse approximation. The system of four reactors with a net total output of 3.8 GW electric is essentially the same as described earlier, however, progress in the analysis has enhanced its credibility and self-consistency. Considerations of environmental and safety aspects and cost estimates are given. (orig.)

  8. Experimental Investigations on Fusion Cutting Stainless Steel with Fiber and CO2 Laser Beams

    Science.gov (United States)

    Stelzer, S.; Mahrle, A.; Wetzig, A.; Beyer, E.

    First results of an experimental study on inert-gas fusion cutting stainless steel with different types of laser are presented. In particular, the cutting capabilities of a fiber and a CO2 laser beam with similar Rayleigh length have been compared as a function of material thickness with respect to achievable maximum cutting speed, cut edge surface roughness and cut kerf geometry. The most interesting finding achieved so far concerns the observation that the cut kerfs are nearly identical in size but differ qualitatively in shape for both laser teypes.

  9. Three dimensional PIC simulation of heavy ion fusion beams: Recent improvements to and applications of WARP

    International Nuclear Information System (INIS)

    The multi-dimensional particle simulation code WARP is used to study the transport and acceleration of space-charge dominated ion beams in present-day and near-term experiments, and in fusion drivers. The algorithms employed in the 3d package and a number of applications have recently been described. In this paper the authors review the general features and major applications of the code. They then present recent developments in both code capabilities and applications. Most notable is modeling of the planned ESQ injector for ILSE, which uses the code's newest features, including subgrid-scale placement of internal conductor boundaries

  10. Niobium thermal - mechanical treatment produced by continuously cast ingots and electron beam fusion

    International Nuclear Information System (INIS)

    Continuonsly cast Nb ingots produced in Brazil by electron beam fusion have been thermally-mechanically processed. These ingots were subjected to a pre-deformation between 0 to 50%, and subsequently treated thermally between 900 to 18000C for 2,3 and 4 hours. Grain refinement was attained by further reduction in area deformations between 42 to 96%, followed by thermal treatments for 3 hours between 810 to 13000C. The results material exhibited an equiaxial grain structure of 50 μm and was tensile tested. These tensile results are compared to the results for niobium produced by traditional commercial practices. (Author)

  11. Estimated nuclear effects in the neutral beam injectors of a large fusion reactor

    International Nuclear Information System (INIS)

    Estimates are given for the nuclear heat loads on the cryopanels, radiation damage (energy deposition rate) in ion gun insulators, and dose equivalent rates from induced activity in the components for the Engineering Test Facility (ETF) neutral beam injectors. The estimates have been obtained by scaling similar results, obtained by careful neutronics analysis for the Tokamak Fusion Test Reactor (TFTR). The approximate nature of the scaling procedure introduces considerable uncertainty in the results, but they are, hopefully, correct to within an order of magnitude and may be substantially more accurate

  12. Beam diagnostics and data acquisition system for ion beam transport line used in applied research

    International Nuclear Information System (INIS)

    Ion beam transport line for applied research on U-400 cyclotron, beam diagnostics and data acquisition system for condensed matter studies are described. The main features of Windows-based real time program are considered

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

    International Nuclear Information System (INIS)

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

  14. Research and development of advanced materials using ion beam

    Energy Technology Data Exchange (ETDEWEB)

    Namba, Susumu [Nagasaki Inst. of Applied Science, Nagasaki (Japan)

    1997-03-01

    A wide range of research and development activities of advanced material synthesis using ion beams will be discussed, including ion beam applications to the state-of-the-art electronics from giant to nano electronics. (author)

  15. Data management in a fusion energy research experiment

    International Nuclear Information System (INIS)

    Present-day fusion research requires extensive support for the large amount of scientific data generated, bringing about three distinct problems computer systems must solve: (1) the processing of large amounts of data in very small time frames; (2) the archiving, analyzing and managing of the entire data output for the project's lifetime; (3) the standardization of data for the exchange of information between laboratories. The computer system supporting General Atomic's Doublet III tokamak, a project funded by the United States Department of Energy, is the first to encounter and address these problems through a system-wide data base structure

  16. Magnetohydrodynamic research in fusion blanket engineering and metallurgical processing

    International Nuclear Information System (INIS)

    A review of recent research activities in liquid metal magnetohydrodynamics (LM-MHDs) is presented in this article. Two major reserach areas are discussed. The first topic involves the thermomechanical design issues in a proposed tokamak fusion reactor. The primary concerns are in the magneto-thermal-hydraulic performance of a self-cooled liquid metal blanket. The second topic involves the application of MHD in material processing in the metallurgical and semiconductor industries. The two representative applications are electromagnetic stirring (EMS) of continuously cast steel and the Czochralski (CZ) method of crystal growth in the presence of a magnetic field. (author) 24 figs., 10 tabs., 136 refs

  17. Data management in a fusion energy research experiment

    Energy Technology Data Exchange (ETDEWEB)

    Glad, A.; Drobnis, D.; McHarg, B.

    1981-07-01

    Present-day fusion research requires extensive support for the large amount of scientific data generated, bringing about three distinct problems computer systems must solve: (1) the processing of large amounts of data in very small time frames; (2) the archiving, analyzing and managing of the entire data output for the project's lifetime; (3) the standardization of data for the exchange of information between laboratories. The computer system supporting General Atomic's Doublet III tokamak, a project funded by the United States Department of Energy, is the first to encounter and address these problems through a system-wide data base structure.

  18. Ion-beam inertial fusion: the requirements posed by target and deposition physics

    International Nuclear Information System (INIS)

    The demonstration of ICF scientific feasibility requires success in target design, driver development and target fabrication. Since these are interrelated, we present here some results of ion beam target studies and relate them to parameters of interest to ion accelerators. Ion deposition physics have long been a well known subject apart from high beam currents. Recent NRL experiments at up to 250 kA/cm2 ions confirm the classical deposition physics now at current densities which are comparable to most ion targets. On the other hand, GSI data at low current density but 1 to 10 MeV/nucleon are continually being accumulated. They have yet to find anomalous results. Relying on target concepts outlined briefly, we report on the energy gain of ion-driven fusion targets as a function of input energy, ion ranges and focal spot radius. We also comment on some consequences of target gain versus driver and reactor requirements

  19. Shielding calculations for the Tokamak Fusion Test Reactor neutral beam injectors

    International Nuclear Information System (INIS)

    Two-dimensional discrete-ordinates calculations have been performed to determine the location and thickness of concrete shielding around the Tokamak Fusion Test Reactor neutral beam injectors. Two sets of calculations were performed, one to determine the dose equivalent rate on the roof and wall of the test cell building when no injectors are present, and one to determine the contribution to the dose equivalent rate at these locations from radiation streaming through the injection duct. Shielding the side and rear of the neutral beam injector with 0.305 and 0.61 m of concrete, respectively, and lining the inside of the test cell wall with an additional layer of concrete having a thickness of 0.305 m and a height above the axis of deuteron injection of 3.10 m is sufficient to maintain the biological dose equivalent rate outside the test cell to approx. 1 mrem/D-T pulse

  20. IAEA consultants' meeting on He-beam data base for alpha particle diagnostics of fusion plasmas

    International Nuclear Information System (INIS)

    The present Report contains the Summary of the IAEA Consultants' Meeting on ''He-Beam Data Base for Alpha Particle Diagnostics of Fusion Plasmas'' which was organized by the Atomic and Molecular Data Unit and held on June 3-5, 1991 at the IAEA Headquarters in Vienna, Austria. The Meeting Proceedings are briefly described and the reports of the Working Groups on the electron- and ion-impact processes are reproduced. A survey on the atomic data needs and required cross section accuracies for helium beam stopping calculations and alpha particle diagnostics of JET- and ITER-like plasmas is included. The conclusions and recommendations of the Meeting regarding the status of present data base (availability and quality) and the needs for its improvement are also given in this Summary Report. (author). Refs, figs and tabs

  1. Beam injection and accumulation method in storage rings for heavy ion fusion

    International Nuclear Information System (INIS)

    A combination of multiturn injection and rf stacking is proposed as an efficient beam injection method in storage rings for heavy ion fusion. Five turn injection in each transverse phase space and four rf stackings give a total of 100 stacking turns. This represents a compromise between the tolerable emittances and momentum spread in the ring. Space charge limitations and coherent beam instabilities are investigated. The most severe limit is found to be the transverse coherent instability, but this can be controlled by the use of sextupole and octupole magnetic fields. Assuming a charge exchange cross section of 1 x 10-15 cm2, the e-folding life time is estimated at 180 ms, while the stacking time is 40 ms

  2. Fusion Energy Advisory Committee report on program strategy for US magnetic fusion energy research

    International Nuclear Information System (INIS)

    The Fusion Energy Advisory Committee (FEAC) was charged by the Department of Energy (DOE) with developing recommendations on how best to pursue the goal of a practical magnetic fusion reactor in the context of several budget scenarios covering the period FY 1994-FY 1998. Four budget scenarios were examined, each anchored to the FY 1993 figure of $337.9 million for fusion energy (less $9 million for inertial fusion energy which is not examined here)

  3. Annual report of the Division of Thermonuclear Fusion Research, JAERI

    International Nuclear Information System (INIS)

    The JFT-2 operating regime was extended to higher toroidal field of 18 kG. Plasma confinements were studied on impurities, instabilities, plasma-wall interaction. Properties of a plasma with a separatrix magnetic surface and plasma behaviour in the scrape-off layer were studied in JFT-2a. In the diagnostics, a grazing-incidence vacuum ultra-violet spectrometer for studies on impurities was completed and put into operation. Several minor improvement and remodelling on the JFT-2 and JFT-2a tokamaks were carried out for the convenience of operation. In the plasma heating, constructions of the JFT-2 neutral injection system and the injector test stand ITS-2 for development of the higher energy ion source were started. The design of 200 kW RF power source for the plasma heating in JFT-2 was also made. Research in surface effects in fusion devices started at April 1, 1975. Experimental apparatus was designed and constructed in this fiscal year. A group for superconducting magnet development for fusion device was set up in January, 1976. Theoretical works continued in the analyses on transport processes, plasma heating, and mhd stabilities with an increasing effort on computational studies. A preliminary design of the 100 MW sub(t) tokamak experimental fusion reactor has been started in April, 1975. At the same time a conceptual design of the 2000 MW sub(t) power reactor was further improved. In the development of large tokamak device of next generation, programs on JT-60 and JT-4 are being carried out. Research and development works and detailed design studies on JT-60 are started based on the preliminary design studies made in the previous year. Preliminary design studies on JT-4 are completed. (auth.)

  4. A view of technology maturity assessment to realize fusion reactor by Japanese young researchers

    International Nuclear Information System (INIS)

    Japanese young researchers who have interest in realizing fusion reactor have analyzed Technology Readiness Levels (TRL) in Young Scientists Special Interest Group on Fusion Reactor Realization. In this report, brief introduction to TRL assessment and a view of TRL assessment against fusion reactor projects conducting in Japan. (J.P.N.)

  5. Laser fusion research at Institute of Laser Engineering, Osaka

    International Nuclear Information System (INIS)

    The primary goal of the Kongoh Project at the Institute of Laser Engineering, Osaka, is to demonstrate the scientific feasibility of laser fusion in the next ten years. In the first phase of the project the glass-laser systems Gekko IV and Gekko XII together with the CO2-laser systems Lekko II and Lekko VIII were used to test the appreciable implosion and to choose the most suitable type of 100-kJ driver. Wavelength scaling of the implosion process is the main objective. In the second phase, a 100-kJ class driver will perform a feasibility test experiment. Basic understanding of laser coupling with plasma has been established in such areas as absorption, stimulated Brillouin scattering, hot-electron and fast-ion generation, and energy transport, by using laser beams of 10.6μm, 1.06μm and 0.53μm wavelength. Implosion dynamics, including compression symmetry and stability of the laser fusion pellet, has been studied by means of time-resolved X-ray shadowgraphy. In ablative-mode compression of a high-aspect-ratio pellet target, an irregularity was observed on the ablation surface during compression. An opacity diagram of the pellet was obtained by time-resolved shadowgraphy and compared with a computer-simulation result. Quantitative determination of plasma parameters of laser-driven spherical targets was performed by X-ray spectroscopic techniques. In the ablative mode, using a thick-polymer-coated pellet, the emission came only from the inside of the pellet, and absorption lines due to resonant photoexcitation and ionization were observed in the outer corona region of the pellet. The core density could be derived reliably by the edge shift of radiative recombination spectrum. Using neon-filled glass microballoons of 26atm., 100 μm dia., with a 10-μm-thick polyethylene coat, the Gekko IV laser of 100ps, 2.5TM, has successfully compressed the core up to 5g.cm-3. The Kongoh Project is beginning to demonstrate the scientific feasibility of laser fusion within the

  6. Annual report of Naka Fusion Research Establishment from April 1, 1997 to March 31, 1998

    International Nuclear Information System (INIS)

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1997 to March 31, 1998. The activities in Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M, and progress in ITER-EDA, including technology development. (J.P.N.)

  7. Annual report of Naka Fusion Research Establishment. From April 1, 1995 to March 31, 1996

    International Nuclear Information System (INIS)

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1995 to March 31, 1996. The activities in Naka Fusion Research Establishment are highlighted by high-temperature plasma research in JT-60U and JFT-2M, and progress in ITER-EDA, including technology development. (author)

  8. Annual report of Naka Fusion Research Establishment from April 1, 1997 to March 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1997 to March 31, 1998. The activities in Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M, and progress in ITER-EDA, including technology development. (J.P.N.)

  9. Annual report of Naka Fusion Research Establishment. From April 1, 1995 to March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Shimada, Michiya; Asakura, Nobuyuki; Moriyama, Shinichi; Yamanishi, Toshihiko; Seki, Masahiro; Takahashi, Ichiro [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment] [eds.

    1996-11-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1995 to March 31, 1996. The activities in Naka Fusion Research Establishment are highlighted by high-temperature plasma research in JT-60U and JFT-2M, and progress in ITER-EDA, including technology development. (author)

  10. Three dimensional simulations of space charge dominated heavy ion beams with applications to inertial fusion energy

    International Nuclear Information System (INIS)

    Heavy ion fusion requires injection, transport and acceleration of high current beams. Detailed simulation of such beams requires fully self-consistent space charge fields and three dimensions. WARP3D, developed for this purpose, is a particle-in-cell plasma simulation code optimized to work within the framework of an accelerator's lattice of accelerating, focusing, and bending elements. The code has been used to study several test problems and for simulations and design of experiments. Two applications are drift compression experiments on the MBE-4 facility at LBL and design of the electrostatic quadrupole injector for the proposed ILSE facility. With aggressive drift compression on MBE-4, anomalous emittance growth was observed. Simulations carried out to examine possible causes showed that essentially all the emittance growth is result of external forces on the beam and not of internal beam space-charge fields. Dominant external forces are the dodecapole component of focusing fields, the image forces on the surrounding pipe and conductors, and the octopole fields that result from the structure of the quadrupole focusing elements. Goal of the design of the electrostatic quadrupole injector is to produce a beam of as low emittance as possible. The simulations show that the dominant effects that increase the emittance are the nonlinear octopole fields and the energy effect (fields in the axial direction that are off-axis). Injectors were designed that minimized the beam envelope in order to reduce the effect of the nonlinear fields. Alterations to the quadrupole structure that reduce the nonlinear fields further were examined. Comparisons were done with a scaled experiment resulted in very good agreement

  11. Three dimensional simulations of space charge dominated heavy ion beams with applications to inertial fusion energy

    Energy Technology Data Exchange (ETDEWEB)

    Grote, D.P.

    1994-11-01

    Heavy ion fusion requires injection, transport and acceleration of high current beams. Detailed simulation of such beams requires fully self-consistent space charge fields and three dimensions. WARP3D, developed for this purpose, is a particle-in-cell plasma simulation code optimized to work within the framework of an accelerator`s lattice of accelerating, focusing, and bending elements. The code has been used to study several test problems and for simulations and design of experiments. Two applications are drift compression experiments on the MBE-4 facility at LBL and design of the electrostatic quadrupole injector for the proposed ILSE facility. With aggressive drift compression on MBE-4, anomalous emittance growth was observed. Simulations carried out to examine possible causes showed that essentially all the emittance growth is result of external forces on the beam and not of internal beam space-charge fields. Dominant external forces are the dodecapole component of focusing fields, the image forces on the surrounding pipe and conductors, and the octopole fields that result from the structure of the quadrupole focusing elements. Goal of the design of the electrostatic quadrupole injector is to produce a beam of as low emittance as possible. The simulations show that the dominant effects that increase the emittance are the nonlinear octopole fields and the energy effect (fields in the axial direction that are off-axis). Injectors were designed that minimized the beam envelope in order to reduce the effect of the nonlinear fields. Alterations to the quadrupole structure that reduce the nonlinear fields further were examined. Comparisons were done with a scaled experiment resulted in very good agreement.

  12. Comparison of electron beam and laser beam powder bed fusion additive manufacturing process for high temperature turbine component materials

    Energy Technology Data Exchange (ETDEWEB)

    Dryepondt, Sebastien N [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pint, Bruce A [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ryan, Daniel [Solar Turbines, Inc., San Diego, CA (United States)

    2016-04-01

    The evolving 3D printer technology is now at the point where some turbine components could be additive manufactured (AM) for both development and production purposes. However, this will require a significant evaluation program to qualify the process and components to meet current design and quality standards. The goal of the project was to begin characterization of the microstructure and mechanical properties of Nickel Alloy X (Ni-22Cr-18Fe-9Mo) test bars fabricated by powder bed fusion (PBF) AM processes that use either an electron beam (EB) or laser beam (LB) power source. The AM materials produced with the EB and LB processes displayed significant differences in microstructure and resultant mechanical properties. Accordingly, during the design analysis of AM turbine components, the specific mechanical behavior of the material produced with the selected AM process should be considered. Comparison of the mechanical properties of both the EB and LB materials to those of conventionally processed Nickel Alloy X materials indicates the subject AM materials are viable alternatives for manufacture of some turbine components.

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

    International Nuclear Information System (INIS)

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

  14. Accelerator and Fusion Research Division annual report, October 1980-September 1981. Fiscal year, 1981

    International Nuclear Information System (INIS)

    Major accomplishments during fiscal year 1981 are presented. During the Laboratory's 50th anniversary celebrations, AFRD and the Nuclear Science Division formally dedicated the new (third) SuperHILAC injector that adds ions as heavy as uranium to the ion repertoire at LBL's national accelerator facilities. The Bevalac's new multiparticle detectors (the Heavy Ion Spectrometer System and the GSI-LBL Plastic Ball/Plastic Wall) were completed in time to take data before the mid-year shutdown to install the new vacuum liner, which passed a milestone in-place test with flying colors in September. The Bevalac biomedical program continued patient treatment with neon beams aimed at establishing a complete data base for a dedicated biomedical accelerator, the design of which NCI funded during the year. Our program to develop alternative Isabelle superconducting dipole magnets, which DOE initiated in FY80, proved the worth of a new magnet construction technique and set a world record - 7.6 Tesla at 1.8 K - with a model magnet in our upgraded test facility. Final test results at LBL were obtained by the Magnetic Fusion Energy Group on the powerful neutral beam injectors developed for Princeton's TFTR. The devices exceeded the original design requirements, thereby completing the six-year, multi-million-dollar NBSTF effort. The group also demonstrated the feasibility of efficient negative-ion-based neutral beam plasma heating for the future by generating 1 A of negative ions at 34 kV for 7 seconds using a newly developed source. Collaborations with other research centers continued, including: (1) the design of LBL/Exxon-dedicated beam lines for the Stanford Synchrotron Radiation Laboratory; (2) beam cooling tests at Fermilab and the design of a beam cooling system for a proton-antiproton facility there; and (3) the development of a high-current betatron for possible application to a free electron laser

  15. Accelerator and Fusion Research Division annual report, October 1980-September 1981. Fiscal year, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, R.K.; Thomson, H.A. (eds.)

    1982-04-01

    Major accomplishments during fiscal year 1981 are presented. During the Laboratory's 50th anniversary celebrations, AFRD and the Nuclear Science Division formally dedicated the new (third) SuperHILAC injector that adds ions as heavy as uranium to the ion repertoire at LBL's national accelerator facilities. The Bevalac's new multiparticle detectors (the Heavy Ion Spectrometer System and the GSI-LBL Plastic Ball/Plastic Wall) were completed in time to take data before the mid-year shutdown to install the new vacuum liner, which passed a milestone in-place test with flying colors in September. The Bevalac biomedical program continued patient treatment with neon beams aimed at establishing a complete data base for a dedicated biomedical accelerator, the design of which NCI funded during the year. Our program to develop alternative Isabelle superconducting dipole magnets, which DOE initiated in FY80, proved the worth of a new magnet construction technique and set a world record - 7.6 Tesla at 1.8 K - with a model magnet in our upgraded test facility. Final test results at LBL were obtained by the Magnetic Fusion Energy Group on the powerful neutral beam injectors developed for Princeton's TFTR. The devices exceeded the original design requirements, thereby completing the six-year, multi-million-dollar NBSTF effort. The group also demonstrated the feasibility of efficient negative-ion-based neutral beam plasma heating for the future by generating 1 A of negative ions at 34 kV for 7 seconds using a newly developed source. Collaborations with other research centers continued, including: (1) the design of LBL/Exxon-dedicated beam lines for the Stanford Synchrotron Radiation Laboratory; (2) beam cooling tests at Fermilab and the design of a beam cooling system for a proton-antiproton facility there; and (3) the development of a high-current betatron for possible application to a free electron laser.

  16. Annual report of Naka Fusion Research Establishment from April 1, 1994 to March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Nagashima, Takashi; Naito, Osamu; Ogiwara, Norio; Saigusa, Mikio; Seki, Masahiro; Murasawa, Michihiko; Uehara, Yusuke [eds.] [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    1995-11-01

    Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1994 to March 31, 1995. The main objectives of the JT-60 experiments are: confinement improvement, impurity control and divertor studies, steady-state studies, and energetic particle physics. JFT-2M experiments progressed in the momentum transport study by applying an external helical field and toroidal momentum input with NBI, and also, the boundary plasma study through the introduction of an electric field in the scrape-off layer (SOL) by the divertor biasing. Progress in the DIII-D experiments was obtained in the studies of divertor radiation, advanced tokamak and VH-mode plasma. As for the fusion technology research, activities are focused on the Research and Development (R and D) for ITER EDA: superconducting magnets, neutral beam heating, radio frequency heating, plasma facing components, reactor structure, remote maintenance, shielding blanket, tritium processing, tritium safety and fusion safety. Based on the Outline Design approved in March 1994 by the ITER Council a sensitivity study was conducted by the new director and JCT in close collaboration with four Home Teams in order to determine the optimum way to achieve a reduction in the cost of ITER while minimizing the impacts regarding its performance margins. Japanese Home Team carried out a part of the ITER design based on task agreements, mainly in the field of vacuum vessel, first wall and blanket, initial assembly, etc. The DREAM tokamak reactor concept was improved focusing on the reactor internals and safety. (J.P.N.).

  17. Annual report of Naka Fusion Research Establishment from April 1, 1994 to March 31, 1995

    International Nuclear Information System (INIS)

    Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1994 to March 31, 1995. The main objectives of the JT-60 experiments are: confinement improvement, impurity control and divertor studies, steady-state studies, and energetic particle physics. JFT-2M experiments progressed in the momentum transport study by applying an external helical field and toroidal momentum input with NBI, and also, the boundary plasma study through the introduction of an electric field in the scrape-off layer (SOL) by the divertor biasing. Progress in the DIII-D experiments was obtained in the studies of divertor radiation, advanced tokamak and VH-mode plasma. As for the fusion technology research, activities are focused on the Research and Development (R and D) for ITER EDA: superconducting magnets, neutral beam heating, radio frequency heating, plasma facing components, reactor structure, remote maintenance, shielding blanket, tritium processing, tritium safety and fusion safety. Based on the Outline Design approved in March 1994 by the ITER Council a sensitivity study was conducted by the new director and JCT in close collaboration with four Home Teams in order to determine the optimum way to achieve a reduction in the cost of ITER while minimizing the impacts regarding its performance margins. Japanese Home Team carried out a part of the ITER design based on task agreements, mainly in the field of vacuum vessel, first wall and blanket, initial assembly, etc. The DREAM tokamak reactor concept was improved focusing on the reactor internals and safety. (J.P.N.)

  18. Highly Repetitive Laser Inertial fusion driver with Tiled Coherent Beam Combination Laser using Stimulated Brillouin Scattering Phase Conjugation Mirrors

    International Nuclear Information System (INIS)

    Full text: In these days, the energy problem is serious in the world. It is necessary to develop a new source of the sustainable energy. In these sustainable energy sources, fusion energy is the most promised energy source. Especially, the laser inertial fusion energy is easy to maintain and easy to increase its scale. However, there are 3 hot problems to achieve the laser inertial fusion energy. To achieve the LIFE, it is necessary to develop 2.5 kJ/10 ns at 10 Hz laser. The Second problem is target injection with high repetition rate and high accuracy. We need to inject the fuel target to the centre of a chamber with accuracy to 20 μm after the fusion reaction. The third problem is the target window coating due to debris from the target implosion. The first and the second problems can be resolved simply by coherent beam combination laser using Stimulated Brillouin Scattering Phase Conjugation Mirrors (SBS-PCM). The 4-beam combination system is built to prove its feasibility to laser inertial fusion energy driver. The input energy of the each sub-beam is 1.032 ± 0.027 mJ, and the output energy of sub-beam is 402.3 ± 1.21 mJ. The standard deviations of the phase differences between the reference beam and other beams were measured to be less than λ/13, during 2,500 shots (250 s), and we will get it better than λ/20 soon. The coherent beam combination using SBS-PCM has additional advantages in LIFE reactor system. In the fusion reaction, target injection is one of the serious problems. The repetition rate of the target injection is ∼ 10 Hz, and the target speed is around 400 m/s. We need the accuracy of target position to 20 μm. Because of the turbulent flow after the prior fusion reaction, it is impossible to inject the target with the accuracy to more than 20 μm. This method can give the accuracy to less than 1 μm even when the turbulence exists in the reactor chamber. In this paper, the authors introduce the tiled coherent beam combining laser using SBS

  19. Early Career. Harnessing nanotechnology for fusion plasma-material interface research in an in-situ particle-surface interaction facility

    Energy Technology Data Exchange (ETDEWEB)

    Allain, Jean Paul [Univ. of Illinois, Champaign, IL (United States)

    2014-08-08

    This project consisted of fundamental and applied research of advanced in-situ particle-beam interactions with surfaces/interfaces to discover novel materials able to tolerate intense conditions at the plasma-material interface (PMI) in future fusion burning plasma devices. The project established a novel facility that is capable of not only characterizing new fusion nanomaterials but, more importantly probing and manipulating materials at the nanoscale while performing subsequent single-effect in-situ testing of their performance under simulated environments in fusion PMI.

  20. Socioeconomic Research on Fusion. SERF 1997-98

    Energy Technology Data Exchange (ETDEWEB)

    Saez, R.; Lechon, Y.; Cabal, H.; Lomba, L.; Palomino, I.; Recreo, F.; Robles, B.; Suanez, A.; Cancio, D. [Ciemat. Madrid (Spain)

    1999-09-01

    In this study the environmental externalities produced in some stages of a hypothetical fusion power plant have been studied. The results are the CIEMAT contribution in the macro task named External costs and benefits of the Socioeconomic Research on Fusion (SERF 1997-98) European project. For the externalities economical assessment the Externe methodology has been applied. Lauffen, sited in the SW of Germany has been selected as the hypothetical location of the power plant. The technology, for two different models, was described by Max Planck Institute and the externalities of the materials manufacturing, power plant construction and operation as well as accidents have been monetarily evaluated. The obtained results revealed that for the plant model which uses cooling water, the prevalent cause of external costs were collective doses produced by the global dispersion of 14C emissions. External costs produced by radiological accidents represent low values, however the preliminary assessment performed for the external impacts caused by the ingestion of contaminated foodstuff and water, point out that a more detailed analysis for this stage, is needed. It should be noted that the results presented in this study, are partial values since other potentially important stages such as disposal of radiological waste and decommissioning of the power plant, have not been included. (Author)

  1. Socioeconomic Research on Fusion. Serf 1997-98

    International Nuclear Information System (INIS)

    Tin this study the environmental externalisation produced in some stages of a hypothetical fusion power plant have been studied. The results are the CIEMAT contribution in the macro task named External costs and benefits of the Socioeconomic Research on Fusion (SERF 1997-98) European project. For the externalisation economical assessment the Externe methodology has been applied. Lauffen, sited in the SW of Germany has been selected as the hypothetical location of the power plant. The technology, for two different models, was described by Max Planck Institute and the externalisation of the materials manufacturing, power plant construction and operation as well as accidents have been monetarily evaluated. The obtained results revealed that for the plant model which uses cooling water, the prevalent cause of external costs were the collective doses produced by the global dispersion of 14C emissions. External costs produced by radiological accidents represent low values, however the preliminary assessment performed for the external impacts caused by the ingestion of contaminated food stuff and water, point out that a more detailed analysis for this stage, is needed. It should be noted that the results presented in this study, are partial values since other potentially important stages such as disposal of radiological waste and decommissioning of the power plant, have not been included. (Author) 30 refs

  2. Configuration of the virtual laboratory for fusion researches in Japan

    International Nuclear Information System (INIS)

    A virtual laboratory system for nuclear fusion researches in Japan known as SNET run by the National Institute for Fusion Science has been in development for the past seven years. Twenty-one remote sites have participated in SNET, which reached a speed of 1 Gbps in April 2009. The SNET is a closed network system based on L2 and L3VPN provided by SINET3, which is a national academic network operated by the National Institute of Informatics. SNET has been successfully supporting the remote participation of various sizes and types of experimental equipments and has also been supporting the remote use of a supercomputer. In this paper, we describe the configuration of SNET, which is overcoming the challenges that arise in virtual laboratories; we mainly explain the remote participation in the experiment. Remarks about the remote participation regarding the ITER activity, massive data transfer, and GRID are also discussed. A data transfer experiment between Japan and France was performed, with the average throughput reaching 880 Mbps on 1 Gbps of bandwidth.

  3. Solenoid transport of a heavy ion beam for warm dense matterstudies and inertial confinement fusion

    Energy Technology Data Exchange (ETDEWEB)

    Armijo, Julien

    2006-10-01

    From February to July 2006, I have been doing research as a guest at Lawrence Berkeley National Laboratory (LBNL), in the Heavy Ion Fusion group. This internship, which counts as one semester in my master's program in France, I was very pleased to do it in a field that I consider has the beauty of fundamental physics, and at the same time the special appeal of a quest for a long-term and environmentally-respectful energy source. During my stay at LBNL, I have been involved in three projects, all of them related to Neutralized Drift Compression Experiment (NDCX). The first one, experimental and analytical, has consisted in measuring the effects of the eddy currents induced by the pulsed magnets in the conducting plates of the source and diagnostic chambers of the Solenoid Transport Experiment (STX, which is a subset of NDCX). We have modeled the effect and run finite-element simulations that have reproduced the perturbation to the field. Then, we have modified WARP, the Particle-In-Cell code used to model the whole experiment, in order to import realistic fields including the eddy current effects and some details of each magnet. The second project has been to take part in a campaign of WARP simulations of the same experiment to understand the leakage of electrons that was observed in the experiment as a consequence to some diagnostics and the failure of the electrostatic electron trap. The simulations have shown qualitative agreement with the measured phenomena, but are still in progress. The third project, rather theoretical, has been related to the upcoming target experiment of a thin aluminum foil heated by a beam to the 1-eV range. At the beginning I helped by analyzing simulations of the hydrodynamic expansion and cooling of the heated material. But, progressively, my work turned into making estimates for the nature of the liquid/vapor two-phase flow. In particular, I have been working on criteria and models to predict the formation of droplets, their size

  4. Radiation hazards in PF-1000 plasma generator fusion research (part 2)

    International Nuclear Information System (INIS)

    This paper focuses on radiation exposures to researchers and technicians involved in fusion research. It is the second article in the series on this topic. It discusses immediate exposures to the ionizing radiation that is generated immediately during fusion research performed on the PF-1000, a dense magnetized plasma generator that is the world's largest. (author)

  5. A high-current four-beam xenon ion source for heavy-ion fusion

    International Nuclear Information System (INIS)

    The growing interest in inertial confinement fusion using heavy ions has elicited from the Los Alamos Scientific Laboratory a proposal to use a multi-channel radiofrequency quadrupole (RFQ) structure for the initial stage of the heavy-ion accelerator. The RFQ would have 4 channels in each module and each channel would accelerate 25 mA of Xe+1. Based on experiments with xenon beam production with a high current duoPlGatron source at Chalk River Nuclear Laboratories, a 245 keV 4-beam xenon injector has been designed for this 4-channel RFQ. The injector is of modular design with 4 small independent plasma sources mounted in a 10 cm square array on a common combined extraction and acceleration column. The electrodes have 4 separate sets of apertures and each channel produces a 29 mA beam for injection into its corresponding RFQ channel. This paper presents a conceptual design for the injector, code calculations for the column electrode design and results of a preliminary test carried out to verify the feasibility of the concept. (author)

  6. Elements of power plant design for inertial fusion energy. Final report of a coordinated research project 2000-2004

    International Nuclear Information System (INIS)

    There are two major approaches in fusion energy research: magnetic fusion energy (MFE) and inertial fusion energy (IFE). The basic physics of IFE (compression and ignition of small fuel pellets containing deuterium and tritium) is being increasingly understood. Based on recent advances by individual countries, IFE has reached a stage at which benefits could be obtained from a coordinated approach in the form of an IAEA Coordinated Research Project (CRP) on Elements of Power Plant Design for Inertial Fusion Energy. This CRP helped Member States to promote the development of plasma/fusion technology transfer and to emphasize safety and environmental advantages of fusion energy. The CRP was focused on interface issues including those related to, - the driver/target interface (e.g. focusing and beam uniformity required by the target), - the driver/chamber interface (e.g. final optics and magnets protection and shielding), - and the target/chamber interface (e.g. target survival during injection, target positioning and tracking in the chamber). The final report includes an assessment of the state of the art of the technologies required for an IFE power plant (drivers, chambers, targets) and systems integration as presented and evaluated by members of the CRP. Additional contributions by cost free invited experts to the final RCM are included. The overall objective of this CRP was to foster the inertial fusion energy development by improving international cooperation. The variety of contributions compiled in this TECDOC reflects, that the goal of stimulating the exchange of knowledge was well achieved. Further the CRP led to the creation of a network, which not only exchanged their scientific results, but also developed healthy professional relations and strong mutual interest in the work of the group members

  7. Beam tomography research at Daresbury Laboratory

    International Nuclear Information System (INIS)

    Beam tomography research at Daresbury Laboratory has focussed on the development of normalised phase space techniques—starting with the idea of sampling tomographic projections at equal phase advances. This idea has influenced the design and operation of the tomography sections at the Photo Injector Test Facility at Zeuthen (PITZ) and at the Accelerator and Lasers in Combined Experiments (ALICE) at Daresbury. We have studied the feasibility of using normalised phase space to measure the effect of space charge. Quadrupole scan measurements are carried out at two different parts of a beamline. Reconstructions at the same location give results that are clearly rotated with respect to each other in normalised phase space. We are able to show that a significant part of this rotation can be attributed to the effect of space charge. We show how the normalised phase space technique can be used to increase the reliability of the Maximum Entropy Technique (MENT). While MENT is known for its ability to work with just a few projections, the accuracy of its reconstructions has seldom been questioned. We show that for typical phase space distributions, MENT could produce results that look quite different from the original. We demonstrate that a normalised phase space technique could give results that are closer to the actual distribution. We also present simpler ways of deriving the phase space tomography formalism and the Maximum Entropy Technique

  8. Research programme on controlled thermonuclear fusion - Synthesis report 2010

    International Nuclear Information System (INIS)

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET). The International Thermonuclear Experimental Reactor (ITER) is being built; the first plasma is expected in 2019. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL participates to EURATOM scientific and technological projects in magnetic confinement physics, through an experimental contribution (the Variable Configuration Tokamak, TCV) and theoretical studies. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. A configuration of type 'snowflakes' could be created, reducing the power deposition at the edge of the plasma. Theoretical studies on turbulence have improved the plasma stability in the TCV. For the first time in the world, TCV could reach a stable plasma, the plasma current being generated using the so-called 'bootstrap' phenomenon. Besides turbulence, studies were focused on heat and particle transport in tokamaks, on an analysis of the equilibrium and magneto-hydrodynamic stability of tokamaks and stellarators, on the application of radiofrequency waves and on the optimization of new confinement configurations. Experiments in the JET facility confirmed the numerical results of theoretical simulations. The TORPEX facility, which is simpler than TCV, allows high space-temporal resolution measurements for the study of turbulences and plasma threads ('blobs'). At the Paul Scherrer Institute (PSI), research topics include superconductivity and materials. The Fusion

  9. Development of high power CO2 laser system 'LEKKO I' for laser fusion research

    International Nuclear Information System (INIS)

    The carbon dioxide laser for nuclear fusion research has the advantages capable of generating high power pulses, obtaining highly efficient excitation because of direct discharge excitation, and employing forced cooling. As such a laser system, the one-beam multi-stage amplifying laser system ''LEKKO I'' has been installed. The outline of its components (an oscillator for generating nanosecond pulses, a pulse shaper, and a succeeding multistage amplifier) and the present development condition are described. Then, the fundamental design techniques for a nanosecond high power laser system are clarified using thus obtained design constants, after finishing the investigations on the limitations due to optical element damage and parasitic oscillation and on the limit of amplifier output. Furthermore, the measured results of the performance characteristics of the laser system ''LEKKO I'' in detail well agreed with the design data. That is, the calculated output value in nanosecond output mode resulted in 101 J through closely taking data in each stage, while the average measured output during actual operation was 100 J, and the maximum output was 113 J. The peak output power was recorded as 100 GW. With the above results, the design of a large scale, higher output CO2 laser system becomes feasible, and the outlook for the development of a driver for nuclear fusion research was obtained. (Wakatsuki, Y.)

  10. Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

  11. Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

    International Nuclear Information System (INIS)

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

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

    International Nuclear Information System (INIS)

    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

  13. Annual report of Fusion Research and Development Directorate of JAEA for FY2008 and FY2009

    International Nuclear Information System (INIS)

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) for FY2008 (from April 1, 2008 to March 31, 2009) and FY2009 (from April 1, 2009 to March 31, 2010), including those performed in collaboration with other research establishments of JAEA, research institutes, and universities. Concerning the ITER project, JAEA was nominated as the domestic agency by the Japanese government after the ITER Agreement took effect, and has fulfilled the obligations. In the development of superconducting conductors, JAEA constructed a technical platform for the fabrication of superconducting conductors for toroidal field (TF) coils ahead of other countries. JAEA immediately started and completed the construction of a plant to fabricate superconducting conductors, and started their fabrication ahead of other countries. In the development of gyrotron high-frequency heating equipment, since only the JAEA satisfies the ITER's procurement specifications among supplier countries, the ITER Organization requested JAEA to conduct confidence tests, and achieved results such as data acquisition that could contribute to the development of the ITER's operational scenario. For the development of neutral beam injectors, advantages of the multi-stage acceleration system developed by JAEA was recognized as a result of comparative experiments with single-stage acceleration systems developed in Europe for the particle acceleration system, and was adopted in the ITER's technical specifications. For the Broader Approach (BA) activities, JAEA was designated as the implementing agency by the Japanese government after the BA Agreement took effect, and has fulfilled the obligations and promoted three projects in the BA activities steadily through domestic cooperation and coordination with Europe. Concerning activities related to the International Fusion Energy

  14. Inertial fusion energy - research at the University of Alberta and a proposed Alberta/Canada Program

    International Nuclear Information System (INIS)

    Fusion Energy is being pursued internationally using a number of different approaches from magnetic confinement energy to inertial confinement fusion (ICF). Recently there has been significant advancement in inertial confinement fusion using laser drivers with the expectation of the demonstration of large fusion yield within the next year or two opening the path to engineering of fusion reactors based on high energy laser drivers. The Laser Plasma Research group at the University of Alberta has been involved in inertial fusion energy (IFE) research for the past few decades. The current status of IFE and the activities of the University of Alberta Research group in this area is reviewed. Funding of IFE related research in Canada has been very limited and Canada has fallen behind in this area. Given the major developments occurring internationally it is time to increase activities in Canada. A plan for an expanded Alberta/Canadian program in IFE in the near future is discussed. (author)

  15. Safety aspects of laser fusion research at the Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    In 1972, the Los Alamos Scientific Laboratory initiated an organized effort - by forming a Laser Research and Technology Division - to investigate the practibility of using the energy in focused laser beams to confine fusion targets of deuterium for thermonuclear burn and subsequent extraction of heat for generating electricity. Criteria for evaluating hazards in high energy laser environments were only in formative stages, and many associated hazards were not contemplated. Fundamental biological data for fast-pulsed lasers was also lacking. This paper describes the control measures instituted and eye-wear developed for the protection of employees. Results of threshold damage experiments are summarized and a programme designed for comprehensive control of the hazards is outlined. To date no biological damage has been experienced by any employee. (author)

  16. On the use of intense ion beams for generating magnetized target fusion plasma

    International Nuclear Information System (INIS)

    Magnetized Target Fusion (MTF) is a concept for creating a burning D-T plasma in a potentially inexpensive system. In essence, the concept involves ion heating on time scales short compared to ion transport times plus strong inhibition of thermal electron transport with a transverse magnetic field. The magnetic field is not intended to confine the ionic component. MTF is an intrinsically pulsed concept. A straightforward analysis of MTF indicates that D-T burning conditions can be achieved in compact plasma volumes with modest initial temperatures, through the use of pulsed power technology. In terms of size, density, temperature, and time scales, MTF occupies a position in phase space that is intermediate between steady MFE schemes and ICF. In terms of cost, it is one to two orders of magnitude less expensive than these. In this paper, the authors consider a possible method for creating the initial conditions adequate for the MTF concept through the use intense ion beam injection

  17. Three-dimensional modeling of beam emission spectroscopy measurements in fusion plasmas

    CERN Document Server

    Guszejnov, D; Pusztai, I; Refy, D; Zoletnik, S; Lampert, M; Nam, Y U; 10.1063/1.4764564

    2013-01-01

    One of the main diagnostic tools for measuring electron density profiles and the characteristics of long wavelength turbulent wave structures in fusion plasmas is Beam Emission Spectroscopy (BES). The increasing number of BES systems necessitated an accurate and comprehensive simulation of BES diagnostics, which in turn motivated the development of the RENATE simulation code that is the topic of this paper. RENATE is a modular, fully three-dimensional code incorporating all key features of BES systems from the atomic physics to the observation, including an advanced modeling of the optics. Thus RENATE can be used both in the interpretation of measured signals and the development of new BES systems. The most important components of the code have been successfully benchmarked against other simulation codes. The primary results have been validated against experimental data from the KSTAR tokamak.

  18. Annual report of Naka Fusion Research Establishment. From April 1,2000 to March 31, 2001

    International Nuclear Information System (INIS)

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 2000 to March 31, 2001. The activities in the Naka Fusion Research Establishment are outstanding at high performance plasma researches in JT-60 and JFT-2M, and development in ITER EDA including technological R and Ds. The JT-60 project aims at contributing to the physics R and D for ITER and establishing the physics basis for a steady state tokamak fusion reactor like SSTR. For the achievement of those objectives, both physical and engineering researches have been done. The JT-60 have continued to be productive in many areas covering performance improvements of high βp ELMy H-mode regime and reversed shear plasma, non-inductive current drive, physics study relevant to improved modes, stabilization of MHD modes, feedback control, disruption study, understandings on energetic particles, and scrape off layer and divertor studies with increased pumping capability. On JFT-2M, advanced and basic research of tokamak plasma is being promoted, including application of the low activation ferritic steel, with the flexibility of a medium-sized device. The pre-testing on compatibility of ferritic steel plates (FPs), covering ∼20% of the inside wall of the vacuum vessel, with plasma was performed, demonstrating no adverse effects on plasmas. Boronization was introduced for the first time in JFT-2M after installation of inside FPs. High-βN discharges (βN up to ∼2.8) were obtained with inside FPs and boronization. Formation of negative electric field at the H-mode transition during ECH was clarified by the heavy ion beam probe (HIBP). The MSE polarimeter system, which is capable of simultaneous measurement of a radial electric field, has been newly developed. In RF experiments, fast wave electric field profile was directly measured for the first time using the beat wave and HIBP. The principal objective of theoretical and

  19. Study of incomplete fusion reaction of 16O-ion beam with 124Sn using particle-gamma coincidence technique

    International Nuclear Information System (INIS)

    In order to study the incomplete fusion dynamics, particle-gamma coincidence experiment for the system 16O + 124Sn at 100 MeV beam energy have been performed. To the best of the knowledge these measurements have been reported first time for this projectile-target system

  20. Fission-reactor experiments for fusion-materials research

    International Nuclear Information System (INIS)

    The US Fusion Materials Program makes extensive use of fission reactors to study the effects of simulated fusion environments on materials and to develop improved alloys for fusion reactor service. The fast reactor, EBR-II, and the mixed spectrum reactors, HFIR and ORR, are all used in the fusion program. The HFIR and ORR produce helium from transmutations of nickel in a two-step thermal neutron absorption reaction beginning with 58Ni, and the fast neutrons in these reactors produce atomic displacements. The simultaneous effects of these phenomena produce damage similar to the very high energy neutrons of a fusion reactor. This paper describes irradiation capsules for mechanical property specimens used in the HFIR and the ORR. A neutron spectral tailoring experiment to achieve the fusion reactor He:dpa ratio will be discussed

  1. Near term commercial opportunities from long range fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Kulcinski, G.L. [Univ. of Wisconsin, Madison, WI (United States)

    1996-12-31

    An alternate approach to the development of safe, clean, and economical fusion energy for the 21st Century is presented. Instead of continuing exclusively on the path of larger and more costly magnetic confinement fusion reactors based on the DT cycle, it is proposed that near term commercial opportunities using fusion plasmas be identified and pursued. Specific examples of such opportunities are given in the areas of the detection of explosives, the production of medical isotopes, and the destruction of long lived fission product isotopes. It is also suggested that a more profitable path to the goal of fusion electricity might be to concentrate on small, simple devices that eventually can burn the more advanced fusion fuels that emit few if any neutrons. Such devices could gain back the public confidence and counter the `fusion is always 50 years away` syndrome. 11 refs., 4 figs., 2 tabs.

  2. Computing for magnetic fusion energy research: The next five years

    International Nuclear Information System (INIS)

    This report considers computing needs in magnetic fusion for the next five years. It is the result of two and a half years of effort by representatives of all aspects of the magnetic fusion community. The report also factors in the results of a survey that was distributed to the laboratories and universities that support fusion. There are four areas of computing support discussed: theory, experiment, engineering, and systems

  3. Developments in bone tissue engineering research for spinal fusion

    OpenAIRE

    van Gaalen, S.M.

    2010-01-01

    Many orthopaedic procedures require fusion of a bony defect. Sometimes a bone graft is needed for this fusion. Autograft bone is considered the golden standard. The harvesting of this bone is time consuming and may have serious side effects, such as chronic donor site pain. Available alternatives are reviewed and discussed based on their benefits and drawbacks. As an alternative, bone Tissue Engineering (TE), i.e. osteoprogenitor cells seeded on porous ceramic scaffolds, for spinal fusion was...

  4. FFUSION yearbook 1997. Annual report of the Finnish fusion research unit. Association EURATOM-TEKES

    Energy Technology Data Exchange (ETDEWEB)

    Karttunen, S.; Paettikangas, T. [eds.] [VTT Energy, Espoo (Finland)

    1998-02-01

    Finnish fusion programme (FFUSION) is one of the eleven national energy research programmes funded by the Technological Development Centre of Finland (TEKES). The FFUSION programme was fully integrated into European Fusion Programme just after Finland joined the European Union. The contract of Association Euratom and Tekes was signed in 1995 and extends to the end of 1999. Finland became a member of JET Joint Undertaking in 1996, other contracts with Euratom include NET agreement and the Staff Mobility Agreement. FFUSION programme with participating research institutes and universities forms the Fusion Research Unit of the Association Euratom-Tekes. This annual report summarises the research activities of the Finnish Research Unit in 1997. The programme consists of two parts: Physics and Technology. The research areas of the physics are: Fusion plasma engineering, and Radio-frequency heating and Plasma diagnostics. The technology is focused into three areas: Fusion reactor materials (first wall components and joining techniques), Remote handling and viewing systems, and Superconductors

  5. FFUSION yearbook 1997. Annual report of the Finnish fusion research unit. Association EURATOM-TEKES

    International Nuclear Information System (INIS)

    Finnish fusion programme (FFUSION) is one of the eleven national energy research programmes funded by the Technological Development Centre of Finland (TEKES). The FFUSION programme was fully integrated into European Fusion Programme just after Finland joined the European Union. The contract of Association Euratom and Tekes was signed in 1995 and extends to the end of 1999. Finland became a member of JET Joint Undertaking in 1996, other contracts with Euratom include NET agreement and the Staff Mobility Agreement. FFUSION programme with participating research institutes and universities forms the Fusion Research Unit of the Association Euratom-Tekes. This annual report summarises the research activities of the Finnish Research Unit in 1997. The programme consists of two parts: Physics and Technology. The research areas of the physics are: Fusion plasma engineering, and Radio-frequency heating and Plasma diagnostics. The technology is focused into three areas: Fusion reactor materials (first wall components and joining techniques), Remote handling and viewing systems, and Superconductors

  6. Assessment report of research and development activities. Activity: 'Fusion research and development' (Interim report)

    International Nuclear Information System (INIS)

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') asked the assessment committee, 'Evaluation Committee of Research and Development Activities for Fusion' (hereinafter referred to as 'Committee') for interim assessment of 'Research and Development of the technical system for extraction of fusion energy,' in accordance with 'General Guideline for the Evaluation of Government R and D Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Fusion Research and Development Directorate (hereinafter referred to as 'FRDD') during the period of four years from October 2005 to August 2009. The Committee evaluated the management and research activities of the FRDD based on the explanatory documents prepared by the FRDD, the oral presentations with questions-and-answers by the Director General and the Deputy Director Generals. (author)

  7. Coherent Tiled 4 Beam Combination by Phase Controlled Stimulated Brillouin Scattering Phase Conjugation Mirrors toward the Practical Laser Fusion Driver

    International Nuclear Information System (INIS)

    Full text: The coherent beam combination using the phase controlled stimulated Brillouin scattering phase conjugate mirrors (SBS-PCMs) is one of the promising techniques for the practical laser fusion drivers. Its ability has been demonstrated experimentally through this work. The phase fluctuations of the titled beams are less than 1/25 wavelength even when the amplifiers are inserted and operated in the beam combining system, which means that this new technique can be applied to combine the currently available lasers such as 100 J/ns/10 Hz for a real laser driver module whose output energy is greater than 5 kJ/ns/10 Hz. (author)

  8. The scientific benefits of inertially confined fusion research

    International Nuclear Information System (INIS)

    A striking feature of 25 years of research into inertially confined fusion (ICF) and inertial fusion energy (IFE) has been its significant impact in other fields of science. Most ICF facilities worldwide are now being used in part to support a wider portfolio of research than simply ICF. Reasons for this trend include the high intrinsic interest of the new science coupled with the relative ease and low marginal cost of adapting the facilities particularly lasers, to carry out experiments with goals other than ICF. The availability at ICF laboratories of sophisticated theory and modeling capability and advanced diagnostics has given added impetus. The expertise of ICF specialists has also triggered more lateral scientific spin-offs leading for example to new types of lasers and to related developments in basic science. In a generic sense, the facilities developed for ICF have made possible study of new regimes of the properties of matter at extremely high-energy density and the interaction of ultraintense light with matter. This general opportunity has been exploited in numerous and diverse specific lines of research. Examples elaborated below include laboratory simulation of astrophysical phenomena; studies of the equation of state (EOS) of matter under conditions relevant to the interior of planets and stars; development of uniquely intense sources of extreme ultraviolet (EUV) to hard x-ray emission, notably the x-ray laser; understanding of the physics of strong field interaction of light and matter; and related new phenomena such as laser-induced nuclear processes and high-field-electron accelerators. Some of these developments have potential themselves for further scientific exploitation such as the scientific use of advanced light sources. There are also avenues for commercial exploitation, for example the use of laser plasma sources in EUV lithography. Past scientific progress is summarized here and projections are made for new science that may flow from the

  9. Annual report of Naka Fusion Research Establishment from April 1, 2001 to March 31, 2002

    International Nuclear Information System (INIS)

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, including those performed in collaboration with other research establishments of JAERI, during the period from April 1, 2001 to March 31, 2002. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, and completion of ITER Engineering Design Activities (EDA) in July 2001, including technology R and D. (J.P.N.)

  10. Annual report of Naka Fusion Research Establishment from April 1, 2001 to March 31, 2002

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Toshiro; Matsumoto, Hiroshi; Moriyama, Shinichi; Tanaka, Fumiya; Tuda, Takashi; Tsuji, Hiroshi (eds.) [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2002-11-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, including those performed in collaboration with other research establishments of JAERI, during the period from April 1, 2001 to March 31, 2002. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, and completion of ITER Engineering Design Activities (EDA) in July 2001, including technology R and D. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

  12. A dual modality phantom for cone beam CT and ultrasound image fusion in prostate implant

    International Nuclear Information System (INIS)

    In transrectal ultrasound (TRUS) guided prostate seed brachytherapy, TRUS provides good delineation of the prostate while x-ray imaging, e.g., C-arm, gives excellent contrast for seed localization. With the recent availability of cone beam CT (CBCT) technology, the combination of the two imaging modalities may provide an ideal system for intraoperative dosimetric feedback during implantation. A dual modality phantom made of acrylic and copper wire was designed to measure the accuracy and precision of image coregistration between a C-arm based CBCT and 3D TRUS. The phantom was scanned with TRUS and CBCT under the same setup condition. Successive parallel transverse ultrasound (US) images were acquired through manual stepping of the US probe across the phantom at an increment of 1 mm over 7.5 cm. The CBCT imaging was done with three reconstructed slice thicknesses (0.4, 0.8, and 1.6 mm) as well as at three different tilt angles (0 deg., 15 deg., 30 deg. ), and the coregistration between CBCT and US images was done using the Variseed system based on four fiducial markers. Fiducial localization error (FLE), fiducial registration error (FRE), and target registration error (TRE) were calculated for all registered image sets. Results showed that FLE were typically less than 0.4 mm, FRE were less than 0.5 mm, and TRE were typically less than 1 mm within the range of operation for prostate implant (i.e., <6 cm to surface of US probe). An analysis of variance test showed no significant difference in TRE for the CBCT-US fusion among the three slice thicknesses (p=0.37). As a comparison, the experiment was repeated with a US-conventional CT scanner combination. No significant difference in TRE was noted between the US-conventional CT fusion and that for all three CBCT image slice thicknesses (p=0.21). CBCT imaging was also performed at three different C-arm tilt angles of 0 deg., 15 deg., and 30 deg. and reconstructed at a slice thickness of 0.8 mm. There is no significant

  13. Implications of NSTX lithium results for magnetic fusion research

    International Nuclear Information System (INIS)

    Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ∼100 g of lithium onto the lower divertor plates between lithium re-loadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, edge localized mode (ELM) control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

  14. Implications of NSTX Lithium Results for Magnetic Fusion Research

    Energy Technology Data Exchange (ETDEWEB)

    M. Ono, M.G. Bell, R.E. Bell, R. Kaita, H.W. Kugel, B.P. LeBlanc, J.M. Canik, S. Diem, S.P.. Gerhardt, J. Hosea, S. Kaye, D. Mansfield, R. Maingi, J. Menard, S. F. Paul, R. Raman, S.A. Sabbagh, C.H. Skinner, V. Soukhanovskii, G. Taylor, and the NSTX Research Team

    2010-01-14

    Lithium wall coating techniques have been experimentally explored on NSTX for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ~ 100 g of lithium onto the lower divertor plates between lithium reloadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, ELM control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

  15. Support and development for remote collaboration in fusion research

    International Nuclear Information System (INIS)

    Major fusion experiments and modeling efforts rely on joint research of scientists from several locations around the world. A variety of software tools are in use to provide remote interactive access to facilities and data are routinely available over wide-area-network connections to researchers. Audio and video communications, monitoring of control room information and synchronization of remote sites with experimental operations all enhance participation during experiments. Remote distributed computing capabilities allow utilization of off-site computers that now help support the demands of control room analyses and plasma modeling. A collaborative software development project is currently using object technologies with CORBA-based communications to build a network executable transport code that further demonstrates the ability to utilize geographically dispersed resources. Development to extend these concepts with security and naming services and possible applications to instrumentation systems has been initiated. An Information Technology Initiative is deploying communication systems, ISDN (telephone) and IP (network) audio/video (A/V) and web browser-based, to build the infrastructure needed to support remote physics meetings, seminars and interactive discussions

  16. Possibility of particle-beam-pumped Ar-Xe laser as an inertial confinement fusion driver

    International Nuclear Information System (INIS)

    Fission-product-beam pumped Ar-Xe laser as a candidate of the driver for a hybrid fission-fusion reactor is studied. Such hybrid reactor can reduce the power requirements for the laser driver. These Ar-Xe lasers have been realized as reactor pumped lasers (RPL) with pulsed reactors. However, high power RPL experiments often face the problem of premature termination of laser output power with respect to the pumping power. Several reasons, including temperature effects, outgassing of impurities from walls have been discussed. Two experiments, elucidating the influence of water vapor impurities in the lasing gas mixture and laser threshold, and the effects of temperature rise in the laser gas on laser output have been performed at the Munich Tandem accelerator, using 100 MeV 32S9+ beams, thus simulating RPL experiments at a pumping power density of ∼ 100 W/cm3. Using these experimental and theoretical results, these RPL-oscillations can be stabilized with high instinctive efficiency. Laser-gas-purification systems and breakeven conditions and related requirements on the hybrid reactor using RPL driver schematically discussed. (author)

  17. Thai Research Reactor (TRR-1/M1) Neutron Beam Measurements

    International Nuclear Information System (INIS)

    Full text: Neutron beam tube of neutron radiography facility at Thai Research Reactor (TRR-1/M1) Thailand Institute of Nuclear Technology (public organization) is a divergent beam. The rectangular open-end of the beam tube is 16 cm x 17 cm while the inner-end is closed to the reactor core. The neutron beam size was measured using 20 cm x 40 cm neutron imaging plate. The measurement at the position 100 cm from the end of the collimator has shown that the beam size was 18.2 cm x 19.0 cm. Gamma ray in neutron the beam was also measured by the identical position using industrial X ray film. The area of gamma ray was 27.8 cm x 31.1 cm with the highest intensity found to be along the neutron beam circumference

  18. Review of neutral beam heating on JET for physics experiments and the production of high fusion performance plasmas

    International Nuclear Information System (INIS)

    The JET neutral beam injection system has proved to be both effective and reliable as a plasma heating device. The ion heating and plasma fuelling characteristics of the system are ideally suited to the production of high fusion performance plasmas while the flexibility in the choice of beam species (H, D, T, 3He or 4He) and the ability to inject into almost any JET plasma configuration allows a wide variety of related physics experiments to be carried out. The capability to inject (for the first time) tritium beams was essential to the successful execution of the first tritium experiments in which 1.7MW of power from D-T fusion reactions was generated. ((orig.))

  19. Developments in bone tissue engineering research for spinal fusion

    NARCIS (Netherlands)

    van Gaalen, S.M.

    2010-01-01

    Many orthopaedic procedures require fusion of a bony defect. Sometimes a bone graft is needed for this fusion. Autograft bone is considered the golden standard. The harvesting of this bone is time consuming and may have serious side effects, such as chronic donor site pain. Available alternatives ar

  20. End product economics and fusion research program priorities

    International Nuclear Information System (INIS)

    It is shown that deuterium based fusion fuels and reactors based on them face severe technological disadvantages in comparison with fission based systems as power sources for central station electric power plants. The author postulates the most plausible deuterium based fusion reactor consistent with the physics of the fusion reaction itself and compares this reactor (called ''OMR-DT'') with existing fission reactors. Since neutrons are the main problem in fusion, the author suggests that a great deal more effort should be given to the study of non-Maxwellian plasmas with the emphasis on neutron-free fuel cycles. The author also suggests that the deuterium based fusion driver may play its best role as a fissile fuel producer

  1. Light ion beam transport research at NRL

    International Nuclear Information System (INIS)

    Transport of light ion beams through low-pressure background gas is under investigation at NRL in support of the light-ion ICF program at Sandia National Laboratories. Scaling experiments and the field solver/orbit code ATHETA have been used to design and construct a focusing, extraction applied-B diode for transport experiments. An active anode source has been developed to provide a high proton fraction in the ion beam and a fast ion turn-on time. A very sensitive Zeeman diagnostic is being developed to determine the net current distribution in the beam/transport system. Both analytical and numerical techniques using several codes are being applied to transport modeling, leading to the capability of full system studies. (author). 1 tab., 5 figs., 10 refs

  2. Perspective on fusion research in China (2) fusion activities in China with special intonation on hybrid reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Lijian, Qiu

    2001-09-01

    Chinese fusion research was started from 1958, but with more clear problem definition it has been set up as the national program for development of the hybrid reactor in 1986. In this paper, it will be described how the organized program is going on.

  3. The International Atomic Energy Agency Activities on Plasma Physics and Nuclear Fusion Research

    International Nuclear Information System (INIS)

    As a global facilitator in the nuclear field, the International Atomic Energy Agency (IAEA) encourages and assists research on controlled nuclear fusion in its Member States by fostering the exchange of scientific and technical information and promoting the exchange of scientists and experts. Within the Division of Physical and Chemical Sciences the Physics Section and the Nuclear Data Section work specifically on topics related to controlled nuclear fusion and organize conferences, technical meetings and workshops that promote information dissemination, training and education. International research is supported within Coordinated Research Projects (CRPs) and Technical Cooperation Projects, all open to all laboratories in the Member States. The International Fusion Research Council is the body that provides advice to the IAEA on programmatic orientations and activities with the view of promoting international cooperation in plasma physics and controlled nuclear fusion research and its applications. The IAEA holds one of the world’s leading fusion meetings. The biannual Fusion Energy Conference gathers more than 1000 participants from more than thirty eight countries and accommodates almost 600 scientific contributions covering the newest topics of research. Publication of the results presented is done in cooperation with the Nuclear Fusion Journal jointly published by the IAEA and IOPP. The IAEA Technical Meetings (TMs) are organised by the Agency and partly hosted by Member States to provide an opportunity for discussion on major concepts of fusion such as magnetic, inertial and pinch, and such as, for instance, steady state operation and burning plasma physics. A particular effort is put in the activities accompanying magnetic confinement research where the IAEA TMs bring together specialists to address specific issues that have a major impact on the success of fusion. Emphasis is put on topics with direct relevance to the effective use of fusion as a future

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

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

  6. FY-2013 FES (Fusion Energy Sciences) Joint Research Target Report

    Energy Technology Data Exchange (ETDEWEB)

    Fenstermacher, M. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Garofalo, A. M. [General Atomics, San Diego, CA (United States); Gerhardt, S. P. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Hubbard, A. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Maingi, R. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Whyte, D. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2013-09-30

    The H-mode confinement regime is characterized by a region of good thermal and particle confinement at the edge of the confined plasma, and has generally been envisioned as the operating regime for ITER and other next step devices. This good confinement is often interrupted, however, by edge-localized instabilities, known as ELMs. On the one hand, these ELMs provide particle and impurity flushing from the plasma core, a beneficial effect facilitating density control and stationary operation. On the other hand, the ELMs result in a substantial fraction of the edge stored energy flowing in bursts to the divertor and first wall; this impulsive thermal loading would result in unacceptable erosion of these material surfaces if it is not arrested. Hence, developing and understanding operating regimes that have the energy confinement of standard Hmode and the stationarity that is provided by ELMs, while at the same time eliminating the impulsive thermal loading of large ELMs, is the focus of the 2013 FES Joint Research Target (JRT): Annual Target: Conduct experiments and analysis on major fusion facilities, to evaluate stationary enhanced confinement regimes without large Edge Localized Modes (ELMs), and to improve understanding of the underlying physical mechanisms that allow acceptable edge particle transport while maintaining a strong thermal transport barrier. Mechanisms to be investigated can include intrinsic continuous edge plasma modes and externally applied 3D fields. Candidate regimes and techniques have been pioneered by each of the three major US facilities (C-Mod, D3D and NSTX). Coordinated experiments, measurements, and analysis will be carried out to assess and understand the operational space for the regimes. Exploiting the complementary parameters and tools of the devices, joint teams will aim to more closely approach key dimensionless parameters of ITER, and to identify correlations between edge fluctuations and transport. The role of rotation will be

  7. Magnetic fusion energy and computers. The role of computing in magnetic fusion energy research and development (second edition)

    International Nuclear Information System (INIS)

    This report documents the structure and uses of the MFE Network and presents a compilation of future computing requirements. Its primary emphasis is on the role of supercomputers in fusion research. One of its key findings is that with the introduction of each successive class of supercomputer, qualitatively improved understanding of fusion processes has been gained. At the same time, even the current Class VI machines severely limit the attainable realism of computer models. Many important problems will require the introduction of Class VII or even larger machines before they can be successfully attacked

  8. Future research program for microprobe external beam

    International Nuclear Information System (INIS)

    The modification of the existing microprobe external beam system for advanced biological experiments have been presented. The model for single ion irradiation has been shown. The model of external measurement chamber and the chamber for testing the outlet windows have been also performed

  9. Annual report of Naka Fusion Research Establishment from April 1, 1998 to March 31, 1999

    International Nuclear Information System (INIS)

    This report provides an overview of research and development activities at the Naka Fusion Research Establishment, JAERI, during the period from April 1, 1998 to March 31, 1999. The activities in the Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M as well as DIII-D (US-Japan collaboration), and progress in ITER EDA, including ITER technology R and D. (J.P.N.)

  10. Annual report of Naka Fusion Research Establishment from April 1, 1998 to March 31, 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    This report provides an overview of research and development activities at the Naka Fusion Research Establishment, JAERI, during the period from April 1, 1998 to March 31, 1999. The activities in the Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M as well as DIII-D (US-Japan collaboration), and progress in ITER EDA, including ITER technology R and D. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

  12. Studies on the feasibility of heavy ion beams for inertial confinement fusion

    International Nuclear Information System (INIS)

    The studies on the ''Feasibility of Heavy Ion Beams for Inertial Confinement'' funded by the German Ministry of Research and Technology have been continued in the same extent as in previous years. This Annual Report summarizes the scientific results of research carried out in the framework of this project at various research laboratories and universities. The principal aims of this research program are the identification and investigation of key issues of the heavy ion ICF concept based on a RF linac driver. Work done in 1983 concentrated on problems of accelerator and target physics: The theoretical investigations on the dynamics of high-intensity beams were continued. For the first time a low frequency RFQ for a high A/q ratio, to be used as a first unit of an injector, was put into operation. Theoretical target studies concentrated more on fundamental physics problems in the ICF targets, and on considerations for the generation of dense plasmas by intense beams of heavy ions. (orig./GG)

  13. Fusion of intraoperative cone-beam CT and endoscopic video for image-guided procedures

    Science.gov (United States)

    Daly, M. J.; Chan, H.; Prisman, E.; Vescan, A.; Nithiananthan, S.; Qiu, J.; Weersink, R.; Irish, J. C.; Siewerdsen, J. H.

    2010-02-01

    Methods for accurate registration and fusion of intraoperative cone-beam CT (CBCT) with endoscopic video have been developed and integrated into a system for surgical guidance that accounts for intraoperative anatomical deformation and tissue excision. The system is based on a prototype mobile C-Arm for intraoperative CBCT that provides low-dose 3D image updates on demand with sub-mm spatial resolution and soft-tissue visibility, and also incorporates subsystems for real-time tracking and navigation, video endoscopy, deformable image registration of preoperative images and surgical plans, and 3D visualization software. The position and pose of the endoscope are geometrically registered to 3D CBCT images by way of real-time optical tracking (NDI Polaris) for rigid endoscopes (e.g., head and neck surgery), and electromagnetic tracking (NDI Aurora) for flexible endoscopes (e.g., bronchoscopes, colonoscopes). The intrinsic (focal length, principal point, non-linear distortion) and extrinsic (translation, rotation) parameters of the endoscopic camera are calibrated from images of a planar calibration checkerboard (2.5×2.5 mm2 squares) obtained at different perspectives. Video-CBCT registration enables a variety of 3D visualization options (e.g., oblique CBCT slices at the endoscope tip, augmentation of video with CBCT images and planning data, virtual reality representations of CBCT [surface renderings]), which can reveal anatomical structures not directly visible in the endoscopic view - e.g., critical structures obscured by blood or behind the visible anatomical surface. Video-CBCT fusion is evaluated in pre-clinical sinus and skull base surgical experiments, and is currently being incorporated into an ongoing prospective clinical trial in CBCT-guided head and neck surgery.

  14. Accelerator and Fusion Research Division. Annual report, October 1978-September 1979

    International Nuclear Information System (INIS)

    Topics covered include: Super HILAC and Bevalac operations; high intensity uranium beams line item; advanced high charge state ion source; 184-inch synchrocyclotron; VENUS project; positron-electron project; high field superconducting accelerator magnets; beam cooling; accelerator theory; induction linac drivers; RF linacs and storage rings; theory; neutral beam systems development; experimental atomic physics; neutral beam plasma research; plasma theory; and the Tormac project

  15. Configuration of the Virtual Laboratory for Fusion Researches in Japan

    International Nuclear Information System (INIS)

    SNET is a virtual laboratory system for nuclear fusion research in Japan, it has been developed since 2001 with SINET3, which is a national academic network backbone operated by National Institute of Computer sciences. Twenty one sites including major Japanese universities, JAEA and NIFS are mutually connected on SNET with the speed of 1 Gbps in 2008 fiscal year. The SNET is a closed network system based on L2 and L3 VPN and is connected to the web through the firewall at NIFS for security maintenance. Collaboration categories in SNET are as follows: the LHD remote participation; the remote use of supercomputer system; the all Japan ST (Spherical Tokamak) research program. For example, the collaborators of the first category in a remote station can control their diagnostic devices at LHD and analyze the LHD data as if they were at the LHD control room. The detail of the network policy is different from each other because each category has its own particular purpose. In October 2008, the Kyushu University and NIFS were connected by L2 VPN. The site was already connected by L3 VPN, but the data transfer rate was rather low. L2 VPN supports the bulk data transfer which is produced by QUEST, the spherical tokamak device at Kyushu University. The wide-area broadcast test began to distribute to remote stations the video which is presented at the front panel of the LHD control room. ITER activity started in 2007 and 'The ITER Remote Experimentation Centre' will be constructed at the Rokkasho village in Japan under ITER-BA agreement. SNET would be useful for distributing the data of ITER to Japanese universities and institutions. (authors)

  16. Research on the fusion diagnosis system of nuclear power plants

    International Nuclear Information System (INIS)

    The work condition of nuclear power plants (NPP) is terrible, so it has faults frequently. In order to guarantee the safety of nuclear power plants, the fusion fault diagnosis system has built. Multi-sensors data fusion technology is applied to the fault diagnosis system. The data fusion level module mainly handles the metrical data of multi-sensors and extracts the feature of faults. The feature level module adopts three parallel neural networks, and its function is to do local diagnosis and to get Basic Probability Assignment (BPA) of D-S evidence theory. The decision fusion level module uses D-S evidence theory. Several main faults of gas turbine rotor and the primary loop of nuclear power plants are diagnosed by the system on the tester and simulator respectively. The analyses of the results indicate that the diagnosis system can diagnose the faults exactly in real time, and the precision is very high. (authors)

  17. 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.

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

    International Nuclear Information System (INIS)

    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.

  19. Annual report of the Fusion Research and Development Center for the period of April 1, 1979 to March 31, 1980

    International Nuclear Information System (INIS)

    Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1979 to March 1980 are described. In Plasma physics research two experiments both related to radio-frequency power injection into tokamak plasmas are to be noted. One is the demonstration of current drive by lower hybrid waves in JFT-2 and the other high efficiency ICRF heating at two-ion hybrid resonance in JFT-2a/DIVA. A multi-MW neutral beam injection system was installed and tested at JFT-2 with heating experiments expected to start shortly. JFT-2a/DIVA was shutdown to make space for the injector. A new ingredient in this area is the initiation of dee plasma experiments in Doublet III at San Diego, USA by JAERI team under US-Japan cooperation agreement. Progress was rapid achieving all experimental objective planned for this period. Construction of JT-60 is in progress as planned. A Mukoyama site where JT-60 and other new facilities will be located was procured in October 1979, which was followed by the construction starts of JT-60 buildings. The completion of JT-60 is expected in fall 1984. The progressive brief summaries are presented in following topics; development of neutral beam and radiofrequency heating system for JT-60, installation of the cluster testing facility with NbTi field coils, and design of tritium handling facility. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

  1. Development status of the 18 GHz superconducting electron cyclotron resonance ion source at National Fusion Research Institute.

    Science.gov (United States)

    You, H J; Jang, S O; Choo, W I; Jung, Y H; Lho, T H; Yoo, S J

    2014-02-01

    A new superconducting 18 GHz electron cyclotron resonance ion source is being developed at the National Fusion Research Institute in South Korea. This source will be dedicated for future application of highly charged ions in the area of matter interaction, diagnostic imaging, and probing. In this paper, we describe the status of the source development consisting of a double electrode biased disk, sputtering systems for metal ion production, diagnostic ports for the extraction region, a variable gap extraction-Einzel lens system, and a low energy beam transport system. PMID:24593495

  2. NASA-NIAC 2001 Phase I Research Grant on Aneutronic Fusion Spacecraft Architecture

    Science.gov (United States)

    Tarditi, Alfonso G. (Principal Investigator); Scott, John H.; Miley, George H.

    2012-01-01

    This study was developed because the recognized need of defining of a new spacecraft architecture suitable for aneutronic fusion and featuring game-changing space travel capabilities. The core of this architecture is the definition of a new kind of fusion-based space propulsion system. This research is not about exploring a new fusion energy concept, it actually assumes the availability of an aneutronic fusion energy reactor. The focus is on providing the best (most efficient) utilization of fusion energy for propulsion purposes. The rationale is that without a proper architecture design even the utilization of a fusion reactor as a prime energy source for spacecraft propulsion is not going to provide the required performances for achieving a substantial change of current space travel capabilities.

  3. Light ion research for inertial confinement fusion at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Light ion beams offer the possibility of a very efficient and low-cost driver for Inertial Confinement Fusion (ICF). The energy deposition is straightforward since the ions deposit their energy in a dense plasma that prevents microscopic instabilities from producing preheating electrons. The difficulty with light ions has been the focusability. In 1984, a proof-of-principle experiment on Proto I, at the same current density and charge density required for inertial fusion on the Particle Beam Fusion Accelerator II (PBFA II), showed that intense ion beams can be focused to the required divergence with the correct local physics. In 1985, the result was scaled to PBFA I at the same current and diode radius required for fusion on PBFA II. PBFA II finished its construction phase with a successful first shot on December 11, 1985. The accelerator is now being characterized and brought to full operational status. The results, to date, of that effort and the relevant data base on beam control and ion source purity will be presented

  4. Annual report of Naka Fusion Research Establishment. From April 1,2000 to March 31, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Kuriyama, Masaaki; Kizu, Kaname; Kusakawa, Fumio; Matsumoto, Hiroshi; Sakamoto, Keishi; Sengoku, Seio (eds.) [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2001-11-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 2000 to March 31, 2001. The activities in the Naka Fusion Research Establishment are outstanding at high performance plasma researches in JT-60 and JFT-2M, and development in ITER EDA including technological R and Ds. The JT-60 project aims at contributing to the physics R and D for ITER and establishing the physics basis for a steady state tokamak fusion reactor like SSTR. For the achievement of those objectives, both physical and engineering researches have been done. The JT-60 have continued to be productive in many areas covering performance improvements of high {beta}{sub p} ELMy H-mode regime and reversed shear plasma, non-inductive current drive, physics study relevant to improved modes, stabilization of MHD modes, feedback control, disruption study, understandings on energetic particles, and scrape off layer and divertor studies with increased pumping capability. On JFT-2M, advanced and basic research of tokamak plasma is being promoted, including application of the low activation ferritic steel, with the flexibility of a medium-sized device. The pre-testing on compatibility of ferritic steel plates (FPs), covering {approx}20% of the inside wall of the vacuum vessel, with plasma was performed, demonstrating no adverse effects on plasmas. Boronization was introduced for the first time in JFT-2M after installation of inside FPs. High-{beta}{sub N} discharges ({beta}{sub N} up to {approx}2.8) were obtained with inside FPs and boronization. Formation of negative electric field at the H-mode transition during ECH was clarified by the heavy ion beam probe (HIBP). The MSE polarimeter system, which is capable of simultaneous measurement of a radial electric field, has been newly developed. In RF experiments, fast wave electric field profile was directly measured for the first time using the beat wave and HIBP. The

  5. Neutron beam research at BARC (India) and international collaboration

    Energy Technology Data Exchange (ETDEWEB)

    Ramanadham, M.; Mukhopadhyay, R. [Solid State Physics Division, Bhabha Atomic Research Centre, Mumbai (India)

    2001-03-01

    Neutron beam research started in India more than four decades ago. Presently, the National Facility for Neutron Beam Research, NFNBR is located in Dhruva, a 100 MW research reactor. The entire facility, including the development of neutron detectors, is the result of indigenous efforts of the participating scientists from Bhabha Atomic Research Centre, BARC. NFNBR is accessible to national and international collaborations, and about forty research groups from various institutions have already availed this facility. Active collaboration with ISIS started since 1984, when the day-1 spectrometer, built at BARC, became operational at ISIS. The collaboration continued with the fabrication, at BARC, of parts for OSIRIS spectrometer. Many neutron beam researchers from BARC have carried out collaborative experiments using the neutron sources at USA, France, Germany, Switzerland, and Japan. (author)

  6. Neutron beam research at BARC (India) and international collaboration

    International Nuclear Information System (INIS)

    Neutron beam research started in India more than four decades ago. Presently, the National Facility for Neutron Beam Research, NFNBR is located in Dhruva, a 100 MW research reactor. The entire facility, including the development of neutron detectors, is the result of indigenous efforts of the participating scientists from Bhabha Atomic Research Centre, BARC. NFNBR is accessible to national and international collaborations, and about forty research groups from various institutions have already availed this facility. Active collaboration with ISIS started since 1984, when the day-1 spectrometer, built at BARC, became operational at ISIS. The collaboration continued with the fabrication, at BARC, of parts for OSIRIS spectrometer. Many neutron beam researchers from BARC have carried out collaborative experiments using the neutron sources at USA, France, Germany, Switzerland, and Japan. (author)

  7. Annual report of the Fusion Research Center for the period of April 1, 1983 to March 31, 1984

    International Nuclear Information System (INIS)

    Research and development activities of the Fusion Research Center (Department of Thermonuclear Fusion Research and Department of Large Tokamak Development) from April 1983 to March 1984 are described. Installation and commissioning of the new tokamak JFT-2M had been completed. The 2nd ICRF heating experiment and LH current drive experiment were started. In the field of plasma theory, the scaling law of the critical beta in a tokamak was obtained and the ICRF heating was analyzed in detail. The first phase of the cooperation of Doublet III will be finished in Sept. 1984. The JT-60 program progressed as scheduled. Installation of the tokamak machine, initiated in Feb. 1983, will be finished in Sept. 1984. The tests of power supply and control system on site and the fabrication of the neutral beam injectors in factory proceeded successfully. Performance tests of prototype injector unit for JT-60 NBI progressed as scheduled. A new advanced source plasma generator was developed to provide a high proton ratio exceeding 90%. Klystrons for JT-60 LH heating achieved the output power of 1 MW for 10 sec. Performance tests of titanium evaporators for JT-60 were completed. The Japanese coil for IEA Large Coil Task was installed in a test facility at ORNL and the partial cool-down was carried out. Construction of the Tritium Process Laboratory was completed. Design studies of the Fusion Experimental Reactor (FER) and INTOR proceeded. (author)

  8. The role and application of ion beam analysis for studies of plasma-facing components in controlled fusion devices

    Science.gov (United States)

    Rubel, Marek; Petersson, Per; Alves, Eduardo; Brezinsek, Sebastijan; Coad, Joseph Paul; Heinola, Kalle; Mayer, Matej; Widdowson, Anna

    2016-03-01

    First wall materials in controlled fusion devices undergo serious modification by several physical and chemical processes arising from plasma-wall interactions. Detailed information is required for the assessment of material lifetime and accumulation of hydrogen isotopes in wall materials. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks, especially in JET with an ITER-Like Wall. IBA techniques play a particularly prominent role here because of their isotope selectivity in the low-Z range (1-10), high sensitivity and combination of several methods in a single run. The role of 3He-based NRA, RBS (standard and micro-size beam) and HIERDA in fuel retention and material migration studies is presented. The use of tracer techniques with rare isotopes (e.g. 15N) or marker layers on wall diagnostic components is described. Special instrumentation, development of equipment to enhance research capabilities and issues in handling of contaminated materials are addressed.

  9. Suppression of Weibel Instabilities in Advanced Fast Ignition Laser Fusion Pellets by Two Cone-Guided Relativistic Laser Beams

    Science.gov (United States)

    Stefan, V.

    2007-11-01

    I propose utilization of two cone-guided relativistic laser beams in antiparallel interaction with the fusion pellet as a novel approach for the suppression of Weibel instabilities in the core of advanced fast ignition pellets.ootnotetextM. Tabak, J. Hammer, M.E. Glinsky, W.L. Kruer, S. C. Wilks, J. Woodworth, E. M. Campbell, and M.D. Perry, Phys. Plasmas 1 (5), 1626 (1994). The propagation of generated suprathermal electron beam toward the core may lead to the appearance of colossal (˜10MG), small scale (L˜velocity of light/local electron plasma frequencyootnotetextV. Stefan, Suppression of Weibel Instabilities by High-Harmonic Electron Bernstein Modes in Advanced Fast Ignition Laser Fusion Pellets.APS-2006. October 30-November 3, 2006; Philadelphia, Pennsylvania. magnetic fields. This would suppress the transport of magnetic fields into the core of the pellet and may eliminate the difficulties in the nonlinear-relativistic treatment of magnetized core plasma.

  10. A proposed method for accurate 3D analysis of cochlear implant migration using fusion of cone beam CT

    Directory of Open Access Journals (Sweden)

    Guido eDees

    2016-01-01

    Full Text Available IntroductionThe goal of this investigation was to compare fusion of sequential cone beam CT volumes to the gold standard (fiducial registration in order to be able to analyze clinical CI migration with high accuracy in three dimensions. Materials and MethodsPaired time-lapsed cone beam CT volumes were performed on five human cadaver temporal bones and one human subject. These volumes were fused using 3D Slicer 4 and BRAINSFit software. Using a gold standard fiducial technique, the accuracy, robustness and performance time of the fusion process were assessed.Results This proposed fusion protocol achieves a sub voxel mean Euclidean distance of 0.05 millimeter in human cadaver temporal bones and 0.16 millimeter when applied to the described in vivo human synthetic data set in over 95% of all fusions. Performance times are less than two minutes.ConclusionHere a new and validated method based on existing techniques is described which could be used to accurately quantify migration of cochlear implant electrodes.

  11. Fusion Canada issue 13

    International Nuclear Information System (INIS)

    A short bulletin from the National Fusion Program. Included in this issue is a report on Canada's plans to participate in the Engineering Design Activities (EDA), bilateral meetings with Canada and the U.S., committee meeting with Canada-Europe, an update at Tokamak de Varennes on Plasma Biasing experiments and boronized graphite tests, fusion materials research at the University of Toronto using a dual beam accelerator and a review of the CFFTP and the CCFM. 2 figs

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

    International Nuclear Information System (INIS)

    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

  13. Progress in heavy ion driven inertial fusion energy: From scaled experiments to the integrated research experiment

    International Nuclear Information System (INIS)

    The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (∼100s Amperesheam) and ion energies (∼1-10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions. and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now being constructed at LBNL. The mission of the HCX will be to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial Fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned

  14. A survey on publications in fusion research and technology science and technology indicators in fusion R and T

    International Nuclear Information System (INIS)

    Scientific publications disseminate research results and are therefore an interesting subject for science and technology analysis. Bibliographic databases contain scientific publications which are indexed and structured. The paper considers Fusion Research and Technology records which are stored in the International Nuclear Information System (INIS) bibliographic database. For the first time, all scientometric and bibliometric information specific to a selected field of science and technology contained in a bibliographic database, using INIS records, is analysed and quantified. A variety of new science and technology indicators which can be used for assessing research and development activities are also presented. (author)

  15. Magnetic fusion energy and computers: the role of computing in magnetic fusion energy research and development

    International Nuclear Information System (INIS)

    This report examines the role of computing in the Department of Energy magnetic confinement fusion program. The present status of the MFECC and its associated network is described. The third part of this report examines the role of computer models in the main elements of the fusion program and discusses their dependence on the most advanced scientific computers. A review of requirements at the National MFE Computer Center was conducted in the spring of 1976. The results of this review led to the procurement of the CRAY 1, the most advanced scientific computer available, in the spring of 1978. The utilization of this computer in the MFE program has been very successful and is also described in the third part of the report. A new study of computer requirements for the MFE program was conducted during the spring of 1979 and the results of this analysis are presented in the forth part of this report

  16. Research on compressive fusion for remote sensing images

    Science.gov (United States)

    Yang, Senlin; Wan, Guobin; Li, Yuanyuan; Zhao, Xiaoxia; Chong, Xin

    2014-02-01

    A compressive fusion of remote sensing images is presented based on the block compressed sensing (BCS) and non-subsampled contourlet transform (NSCT). Since the BCS requires small memory space and enables fast computation, firstly, the images with large amounts of data can be compressively sampled into block images with structured random matrix. Further, the compressive measurements are decomposed with NSCT and their coefficients are fused by a rule of linear weighting. And finally, the fused image is reconstructed by the gradient projection sparse reconstruction algorithm, together with consideration of blocking artifacts. The field test of remote sensing images fusion shows the validity of the proposed method.

  17. Laser development for laser fusion applications research. Progress report, October 1977--March 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-06-01

    Research progress is reported on three laser programs being developed for the commercialization of laser-fusion energy. The lasers include iodine, hydrogen fluoride and Group VI atoms (e.g., O, S, Se, Te). (TFD)

  18. Laser development for laser fusion applications research. Progress report, October 1977--March 1978

    International Nuclear Information System (INIS)

    Research progress is reported on three laser programs being developed for the commercialization of laser-fusion energy. The lasers include iodine, hydrogen fluoride and Group VI atoms (e.g., O, S, Se, Te)

  19. Research of Multi-sensor Images Based on Color Fusion Methods

    Directory of Open Access Journals (Sweden)

    Chunlong Yao

    2013-11-01

    Full Text Available With the development of image sensor technology, multi-sensor image fusion technology emerged and was widely used in the field of military surveillance, medical diagnosis, remote sensing, intelligent robot and so on. However, the current image fusion technology mainly focuses on the research of gray images, the color image fusion is rarely. Because color image contains more information compared with gray image, the research on color image fusion technology is becoming more and more urgent. In this paper, the realization of several typical color image fusion algorithms were discussed, the principle and their respective advantages and disadvantages were analyzed. Secondly, according to the different characteristics of visible image and infrared image, this paper proposes a color image fusion algorithm based on Curve let transform, this algorithm will combine visible image, infrared image with its negative respectively fusion, color mapping rules are in couple with the human visual characteristics. Experiments show that color fusion images obtained are richer in color, they contains more details and recognize easily.

  20. Research and development plan of fusion technologies in JAERI toward DEMO reactors

    International Nuclear Information System (INIS)

    In accordance with the 'Third Phase Basic Program on Fusion Research and Development' established by the Fusion Council of the Japan Atomic Energy Commission, research and development (R and D) of fusion technologies aim at realization of two elements: development of ITER key components and their improvement for higher performances; and construction of sound technical basis of fusion nuclear technologies essential for fusion energy utilization. JAERI has been assigned in the Third Phase Basic Program as a responsible institute for developing the above two elements, and accordingly has been implementing technology R and Ds categorized in the following three areas: R and D for ITER construction and operation; R and D for ITER utilization (blanket testing in ITER) and toward DEMO; and R and D on basic fusion technologies. The present report reviews the status and the plan of fusion technology R and Ds in the latter two areas, and presents the technical objectives, technical issues, status of R and D and near-term R and D plans for: breeding blankets; structural materials; the IFMIF program; improvements of the key ITER components for higher performances toward DEMO; and basic fusion technologies. (author)

  1. Multimodal options for materials research to advance the basis for fusion energy in the ITER era

    Science.gov (United States)

    Zinkle, S. J.; Möslang, A.; Muroga, T.; Tanigawa, H.

    2013-10-01

    Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. Due to differences in national timelines and fusion device concepts, a parallel-track (multimodal) approach is currently being used for developing fusion energy. An overview is given of the current state-of-the-art of major candidate materials systems for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to high-temperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two inter-related overarching objectives of fusion materials research to be performed in the next decade: (1) understanding materials science phenomena in the demanding DT fusion energy environment, and (2) application of this knowledge to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high-performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.

  2. Modifications of the laser beam coherence inertial confinement fusion plasmas; Modifications des proprietes de coherence des faisceaux laser dans les plasmas de fusion par confinement inertiel

    Energy Technology Data Exchange (ETDEWEB)

    Grech, M

    2007-06-15

    Inertial confinement fusion by laser requires smoothed laser beam with well-controlled coherence properties. Such beams are made of many randomly distributed intensity maxima: the so-called speckles. As the laser beam propagates through plasma its temporal and spatial coherence can be reduced. This phenomenon is called plasma induced smoothing. For high laser intensities, instabilities developing independently inside the speckles are responsible for the coherence loss. At lower intensities, only collective effects, involving many speckles, can lead to induced smoothing. This thesis is a theoretical, numerical and experimental study of these mechanisms. Accounting for the partially incoherent behavior of the laser beams requires the use of statistical description of the laser-plasma interaction. A model is developed for the multiple scattering of the laser light on the self-induced density perturbations that is responsible for a spreading of the temporal and spatial spectra of the transmitted light. It also serves as a strong seed for the instability of forward stimulated Brillouin scattering that induces both, angular spreading and red-shift of the transmitted light. A statistical model is developed for this instability. A criterion is obtained that gives a laser power (below the critical power for filamentation) above which the instability growth is important. Numerical simulations with the interaction code PARAX and an experiment performed on the ALISE laser facility confirm the importance of these forward scattering mechanisms in the modification of the laser coherence properties. (author)

  3. A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

    OpenAIRE

    Mitsuru Kikuchi

    2010-01-01

    Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented. In 1990, a steady-state tokamak reactor (SSTR) best utilizing the bootstrap current was developed. Since then, significant efforts have been made in major tokamaks, including JT-60U, exploring advanced regimes relevant to the steady state operation of tokamaks. In this paper, the fund...

  4. Inverse time-of-flight spectrometer for beam plasma research

    International Nuclear Information System (INIS)

    The paper describes the design and principle of operation of an inverse time-of-flight spectrometer for research in the plasma produced by an electron beam in the forevacuum pressure range (5–20 Pa). In the spectrometer, the deflecting plates as well as the drift tube and the primary ion beam measuring system are at high potential with respect to ground. This provides the possibility to measure the mass-charge constitution of the plasma created by a continuous electron beam with a current of up to 300 mA and electron energy of up to 20 keV at forevacuum pressures in the chamber placed at ground potential. Research results on the mass-charge state of the beam plasma are presented and analyzed

  5. Inverse time-of-flight spectrometer for beam plasma research

    Energy Technology Data Exchange (ETDEWEB)

    Yushkov, Yu. G., E-mail: yuyushkov@gmail.com; Zolotukhin, D. B.; Tyunkov, A. V. [Tomsk State University of Control Systems and Radioelectronics, 40 Lenin Ave., Tomsk 634050 (Russian Federation); Oks, E. M. [Tomsk State University of Control Systems and Radioelectronics, 40 Lenin Ave., Tomsk 634050 (Russian Federation); Institute of High Current Electronics SB RAS, 2/3, Akademichesky Ave., Tomsk 634055 (Russian Federation); Savkin, K. P. [Institute of High Current Electronics SB RAS, 2/3, Akademichesky Ave., Tomsk 634055 (Russian Federation)

    2014-08-15

    The paper describes the design and principle of operation of an inverse time-of-flight spectrometer for research in the plasma produced by an electron beam in the forevacuum pressure range (5–20 Pa). In the spectrometer, the deflecting plates as well as the drift tube and the primary ion beam measuring system are at high potential with respect to ground. This provides the possibility to measure the mass-charge constitution of the plasma created by a continuous electron beam with a current of up to 300 mA and electron energy of up to 20 keV at forevacuum pressures in the chamber placed at ground potential. Research results on the mass-charge state of the beam plasma are presented and analyzed.

  6. Introduction of International Fusion Energy Research Centre (IFERC) project

    International Nuclear Information System (INIS)

    A mission of the IFERC project is to accelerate the development of thermonuclear demo reactor by joining and contributing to the ITER project. It consists of three subprojects, the design of thermonuclear demo reactor, the computer simulation study on thermonuclear fusion and the remote experiment for ITER. In the present paper, present status, organization and future prospect of the project are described. (author)

  7. Remote-handling challenges in fusion research and beyond

    Science.gov (United States)

    Buckingham, Rob; Loving, Antony

    2016-05-01

    Energy-producing nuclear fusion reactions taking place in tokamaks cause radiation damage and radioactivity. Remote-handling technology for repairing and replacing in-vessel components has evolved enormously over the past two decades -- and is now being deployed elsewhere too.

  8. Lawrence Livermore Laboratory heavy ion fusion program

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-12-29

    In the large fusion program at Livermore we are actively doing research in most areas of inertial confinement fusion. The areas in which we are funded for research specific to heavy ion fusion are: (1) target design; (2) energy conversion chamber design and (3) ion beam propagation in the combustion chamber. There are two main thrusts to the target design effort: (1) development of targets which are optimally suited to heavy ion fusion power production and (2) fundamental studies of the beam-target interaction.

  9. Annual report of Naka Fusion Research Establishment from April 1, 2002 to March 31, 2003

    International Nuclear Information System (INIS)

    This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2002 to 31 March, 2003. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction. JT-60 program has continued to produce fruitful knowledge and understanding necessary to achieve reactor relevant performances of tokamak fusion devices. JFT-2M has made contributions in more basic areas of tokamak plasma research and development in pursuit of high performance plasma. The objectives of JT-60 research have been more shifted to physics R and Ds in support of the International Thermonuclear Experimental Reactor (ITER) and establishment of physics basis for a steady state tokamak fusion reactor like SSTR as a fusion power demonstration plant. In JFT-2M, the advanced material tokamak experiment program has been carried out to test the low activation ferritic steel for development of the structural material for a fusion reactor. In the area of theories and analyses, significant progress has been made in understanding of the ITB, energy confinement scaling in ITB plasmas, MHD equilibrium in the current hole region, asymmetric feature of divertor plasmas and the divertor detachment. In addition, through the project of numerical experiment on tokamak, the mechanism of the ion temperature gradient mode was clarified by particle simulations. The physics of divertor plasma was also studied by particle simulations. R and Ds of fusion reactor technologies have been carried out both to further improve technologies necessary for ITER construction, and to accumulate

  10. Research and Realization of Medical Image Fusion Based on Three-Dimensional Reconstruction

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    A new medical image fusion technique is presented. The method is based on three-dimensional reconstruction. After reconstruction, the three-dimensional volume data is normalized by three-dimensional coordinate conversion in the same way and intercepted through setting up cutting plane including anatomical structure, as a result two images in entire registration on space and geometry are obtained and the images are fused at last.Compared with traditional two-dimensional fusion technique, three-dimensional fusion technique can not only resolve the different problems existed in the two kinds of images, but also avoid the registration error of the two kinds of images when they have different scan and imaging parameter. The research proves this fusion technique is more exact and has no registration, so it is more adapt to arbitrary medical image fusion with different equipments.

  11. A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

    Directory of Open Access Journals (Sweden)

    Mitsuru Kikuchi

    2010-11-01

    Full Text Available Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented. In 1990, a steady-state tokamak reactor (SSTR best utilizing the bootstrap current was developed. Since then, significant efforts have been made in major tokamaks, including JT-60U, exploring advanced regimes relevant to the steady state operation of tokamaks. In this paper, the fundamentals of fusion and plasma confinement, and the concepts and research on current drive and MHD stability of advanced tokamaks towards realization of a steady-state tokamak reactor are reviewed, with an emphasis on the contributions of the JAEA. Finally, a view of fusion energy utilization in the 21st century is introduced.

  12. Interaction of a self-focused laser beam with a DT fusion target in a plasma-loaded cone-guided ICF scheme

    Science.gov (United States)

    Saedjalil, N.; Mehrangiz, M.; Jafari, S.; Ghasemizad, A.

    2016-06-01

    In this paper, the interaction of a self-focused laser beam with a DT fusion target in a plasma-loaded cone-guided ICF scheme has been presented. We propose here to merge a plasma-loaded cone with the precompressed DT target in order to strongly focus the incident laser beam on the core to improve the fusion gain. The WKB approximation is used to derive a differential equation that governs the evolution of beamwidth of the incident laser beam with the distance of propagation in the plasma medium. The effects of initial plasma and laser parameters, such as initial plasma electron temperature, initial radius of the laser beam, initial laser beam intensity and plasma density, on self-focusing and defocusing of the Gaussian laser beam have been studied. Numerical results indicate that with increasing the plasma frequency (or plasma density) in the cone, the laser beam will be self-focused noticeably, while for a thinner laser beam (with small radius), it will diverge as propagate in the cone. By evaluating the energy deposition of the relativistic electron ignitors in the fuel, the importance of electron transportation in the cone-attached shell was demonstrated. Moreover, by lessening the least energy needed for ignition, the electrons coupling with the pellet enhances. Therefore, it increases the fusion efficiency. In this scheme, with employing a plasma-loaded cone, the fusion process improves without needing an ultrahigh-intensity laser beam in a conventional ICF.

  13. Design of a Fast Neutral He Beam System for Feasibility Study of Charge-Exchange Alpha-Particle Diagnostics in a Thermonuclear Fusion Reactor

    CERN Document Server

    Shinto, Katsuhiro; Kitajima, Sumio; Kiyama, Satoru; Nishiura, Masaki; Sasao, Mamiko; Sugawara, Hiroshi; Takenaga, Mahoko; Takeuchi, Shu; Wada, Motoi

    2005-01-01

    For alpha-particle diagnostics in a thermonuclear fusion reactor, neutralization using a fast (~2 MeV) neutral He beam produced by the spontaneous electron detachment of a He- is considered most promising. However, the beam transport of produced fast neutral He has not been studied, because of difficulty for producing high-brightness He- beam. Double-charge-exchange He- sources and simple beam transport systems were developed and their results were reported in the PAC99* and other papers.** To accelerate an intense He- beam and verify the production of the fast neutral He beam, a new test stand has been designed. It consists of a multi-cusp He+

  14. Neutron beam facilities at the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

  15. Neutron beam facilities at the Australian Replacement Research Reactor

    International Nuclear Information System (INIS)

    Australia is building a research reactor to replace the HIFAR reactor at Lucas Heights by the end of 2005. Like HIFAR, the Replacement Research Reactor will be multipurpose with capabilities for both neutron beam research and radioisotope production. It will be a pool-type reactor with thermal neutron flux (unperturbed) of 4 x 1014 n/cm2/sec and a liquid D2 cold neutron source. Cold and thermal neutron beams for neutron beam research will be provided at the reactor face and in a large neutron guide hall. Supermirror neutron guides will transport cold and thermal neutrons to the guide hall. The reactor and the associated infrastructure, with the exception of the neutron beam instruments, is to be built by INVAP S.E. under contract. The neutron beam instruments will be developed by ANSTO, in consultation with the Australian user community. This status report includes a review the planned scientific capabilities, a description of the facility and a summary of progress to date. (author)

  16. The synchrotron beam, a new dimension for contrast media research?

    Science.gov (United States)

    Elleaume, H; Charvet, A M; Le Bas, J F

    1997-01-01

    Synchrotron sources can provide intense, collimated and tunable X-ray beams suitable for medical imaging and research, allowing the use of monochromatic X-rays for human examinations. At the European Synchrotron Radiation Facility (ESRF), a beam line dedicated to medical research is under commissioning. Two imaging programs are being developed, for coronary angiography and cerebral CT. The new monochromatic imaging systems should improve image contrast and provide better image quantification. The properties of synchrotron radiation are described, as well as the instrumentation of the medical beam line and its 2 imaging programs. The new possibilities offered by synchrotron radiation for contrast media research are discussed, the improvement on concentration measurement precision achievable is underlined. PMID:9240078

  17. E-beam facility for collaborative research

    International Nuclear Information System (INIS)

    An indigenously developed Microtron facility at Mangalore University is being used for variety of research activities in interdisciplinary areas of science and technology. The unique facility with 8 MeV electrons, intense Bremsstrahlung photons and neutrons of moderate flux facilitates a number of co-ordinated R and D programs in collaboration with universities and national laboratories. A bird's eye view of all these activities along with a few sample results is presented in this paper. (author)

  18. Validation in Fusion Research: Towards Guidelines and Best Practices

    CERN Document Server

    Terry, P W; Leboeuf, J -N; McKee, G R; Mikkelsen, D R; Nevins, W M; Newman, D E; Stotler, D P

    2008-01-01

    Because experiment/model comparisons in magnetic confinement fusion have not yet satisfied the requirements for validation as understood broadly, a set of approaches to validating mathematical models and numerical algorithms are recommended as good practices. Previously identified procedures, such as verification, qualification, and analysis of error and uncertainty, remain important. However, particular challenges intrinsic to fusion plasmas and physical measurement therein lead to identification of new or less familiar concepts that are also critical in validation. These include the primacy hierarchy, which tracks the integration of measurable quantities, and sensitivity analysis, which assesses how model output is apportioned to different sources of variation. The use of validation metrics for individual measurements is extended to multiple measurements, with provisions for the primacy hierarchy and sensitivity. This composite validation metric is essential for quantitatively evaluating comparisons with ex...

  19. Neutron beam applications using low power research reactor Malaysia perspectives

    International Nuclear Information System (INIS)

    The TRIGA MARK II Research reactor at the Malaysian Institute for Nuclear Research (MINT) was commissioned in July 1982. Since then various works have been performed to utilise the neutrons produced from this steady state reactor. One area currently focussed on is the utilisation of neutron beam ports available at this 1MW reactor. Projects undertaken are the development and utilisation of the Neutron Radiography (myNR), Small Angle Neutron Scattering (mySANS) and Boron Neutron Capture Therapy (BNCT) - preliminary study. In order to implement active research programmes, a group comprised of researcher from research institutes and academic institutions, has formed: known as Malaysian Reactor Interest Group (MRIG). This paper describes the recent status the above neutron beam facilities and their application in industrial, health and material technology research and education. The related activities of MRIG are also highlighted. (author)

  20. Thermal hydraulics and mechanics research on fusion blanket system

    International Nuclear Information System (INIS)

    In-vessel components such as Blanket and Divertor in a fusion reactor have a function of exhausting high heat and particle loads in order to maintain the structural soundness of the reactor. In the International Thermonuclear Experimental Reactor called ITER, build by ITER Organization under the framework of collaboration of seven parties including Japan, there are two kinds of blanket systems will be install. One is a shield blanket, which consists of a first wall (FW) and a block module shielding against neutron flux to a vacuum chamber and a superconducting magnet system. The other blanket system is called as a Test Blanket Module (TBM). TBM is a kind of prototype blanket for a fusion power plant and has functions of breeding of tritium (T) and extraction of energy from fusion plasma. TBM consists of FW and T-breeding / neutron (n)-multiplier zone. A concept of TBM developed by JAEA is water-cooled pebble-bed type, which means that FW and other structures are cooled by pressurized high temperature water and T-breeding / n-multiplier zone consists of multiple layers of pebble bed made of T-breeding and n-multiplier material. This paper describes the status of R and Ds on FW and pebble beds from the view of thermo-hydraulics and mechanics. (author)