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Sample records for naka fusion research

  1. 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)

  2. 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.)

  3. 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.)

  4. 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.)

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

    International Nuclear Information System (INIS)

    Hoshino, Katsumichi; Umeda, Naotaka; Tsuji, Hiroshi; Yoshida, Hidetoshi; Nagami, Masayuki

    2004-11-01

    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.)

  6. Annual report of Naka Fusion Research Establishment. From April 1, 1996 to March 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Shimizu, Masatsugu; Ide, Shunsuke; Matsukawa, Makoto; Kurihara, Ryoichi; Koizumi, Koichi; Takahashi, Ichiro [eds.] [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    1997-10-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1996 to March 31, 1997. 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. The objectives of the JT-60 project are to contribute to the ITER physics R and D and to establish the physics basis for a steady state tokamak fusion reactor like SSTR. Objectives of the JFT-2M program are (1) advanced and basic researches for the development of high-performance plasmas for nuclear fusion and (2) contribution to the physics R and D for ITER, with a merit of flexibility of a medium-size device. The Detailed Design Report (DDR) of ITER was issued by the Director in November 1996, as the basis of the Final Design Report (FDR). After the formal review by the Technical Advisory Committee (TAC), the DDR was officially accepted by the ITER Council at its 11th Meeting held in December 1996. The DDR is composed of various technical documents on the detailed design of plasma parameters, tokamak components, plant system and tokamak building. The major results of safety analyses described in the Non-site Specific Safety Report (NSSR)-1 was also included in the DDR. The FDR will be prepared by the end of 1997 for presentation at the ITER Council. (J.P.N.)

  7. Annual report of Naka Fusion Research Establishment from April 1, 2002 to March 31, 2003

    International Nuclear Information System (INIS)

    Tsuji, Hiroshi; Hamamatsu, Kiyotaka; Matsumoto, Hiroshi; Yoshida, Hidetoshi

    2003-11-01

    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

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

    International Nuclear Information System (INIS)

    Nagashima, Takashi; Naito, Osamu; Ogiwara, Norio; Saigusa, Mikio; Seki, Masahiro; Murasawa, Michihiko; Uehara, Yusuke

    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.)

  9. 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.).

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

    International Nuclear Information System (INIS)

    Kuriyama, Masaaki; Kizu, Kaname; Kusakawa, Fumio; Matsumoto, Hiroshi; Sakamoto, Keishi; Sengoku, Seio

    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 β 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 ∼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-β N discharges (β N 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

  11. 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

  12. Annual report of Naka Fusion Research Establishment from April 1, 2004 to March 31, 2005

    International Nuclear Information System (INIS)

    Yamamoto, Takumi; Sato, Masayasu; Kudo, Yusuke; Shu, Wataru; Yoshida, Hidetoshi

    2005-09-01

    This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment during the period from 1 April, 2004 to 31 March, 2005, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In the JT-60 research program, the pulse length of the tokamak discharge was extended successfully up to 65 s in FY 2003. In FY 2004, following the successful results, optimization of long pulse discharges was continued. The pulse length of the negative-ion based neutral beam injection system has reached up to 25 s with an injection power of 1 MW. In the electron cyclotron wave system, the pulse length has also extended up to 45 s with an RF power of 0.35 MW by using four gyrotrons in a series operation. Sustainment of higher normalized β of β N >2.3 for 22.3 s, or β N >2.5 for 15.5 s has been achieved by exploiting available plasma heating systems. This discharge exhibits not only the high β N , but also high confinement improvement with the H factor of H 89P =1.9-2.3 and high normalized fusion performance of G≡H 89P β N /q 95 2 =0.4-0.5 during the sustainment, where q 95 is a safety factor at the edge. G-0.4 corresponds to the fusion energy gain of Q=10 for the ITER standard scenario. The H-mode plasma with H 89P -1.4 has been maintained for about 30 s, although degradation of the performance was observed at the later half of the discharge. In the reversed shear plasmas, the operation regime was successfully extended. Demonstration of neoclassical tearing mode stabilization and improvement of plasma performance in the high beta region (β N - 3) has been performed using local current drive by the second harmonic electron cyclotron waves. In addition, a real-time control system of safety factor profile has been developed. The design of National Centralized Tokamak (NCT), which is the superconducting modification of JT-60, progressed both in physics and

  13. Annual report of the Naka Fusion Research Establishment for the period of April 1, 1985 to March 31, 1986

    International Nuclear Information System (INIS)

    1987-02-01

    Research and development activities of the Naka Fusion Research Establishment for the period of April 1985 to March 1986 are described. The JT-60 tokamak machine was completed in April 1985 after a seven-year construction period, and the first plasma operation was achieved on April 8, 1985. Initial experiments with Joule-heated plasmas were performed for three months from April to June 1985 and confirmed tokamak discharges of sufficient plasma current and density as required for additional heating in the divertor configuration. In JFT-2M experiments on beam and ICRF heated plasmas, H-mode discharges with good confinement characteristics were achieved in open divertor configurations. The Doublet III device had been modified into D-III D with a large deeshaped cross-section. The first plasma was obtained in February 1986. The development of a numerical tokamak code TRITON-II was continued. Plasma-surface interaction studies and vacuum technology development were continued. In the study of plasma heating technology, programmable control of the neutral beam energy was demonstrated in a proto-type injector unit. Negative hydrogen ion beams of 25 keV, 0.1 A were extracted by using multiaperture extraction grid. Research was also carried out on improvements of RF coupling system with emphasis on RF breakdown phenomena in a pill box type ceramic window. In the development of superconducting magnets, generation of a 12T magnetic field was demonstrated by the Test Module Coils. The fabrication of the Demonstration Poloidal Coil was started. Preliminary tritium tests on JAERI's proto-type Pd-diffuser and ceramic electrolysis cell had been successfully carried out in the TSTA at LANL. The design study of the Fusion Experimental Reactor was continued. A wide range of scoping studies was also made to evaluate cost/benefits effects. INTOR design studies were concentrated on tokamak innovations. (J.P.N.)

  14. Annual report of the Naka Fusion Research Establishment for the period of April 1, 1990 to March 31, 1991

    International Nuclear Information System (INIS)

    1991-10-01

    R and D activities of the Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1990 to March 31, 1991. Since the shutdown of JT-60 in November 1989, the reconstruction work of the JT-60 device was continued until the end of March 1991. In the JT-60 Upgrade, the poloidal field coils and vacuum vessel were renewed and the plasma current was planned to increase up to 6 MA with lower single null divertor. The divertor plates were designed to be toroidally continuous and to use high-heat-conduction C/C composite materials. Another objective of JT-60U is to facilitate tokamak experiments with deuterium as the working gas. In the JFT-2M program, a system for divertor bias experiments was brought into operation and initial experiments were started to study its effects on plasma discharges. Effects of ergodic magnetic limiter on H-modes were examined and stationary H-modes were obtained under the control of ergodic magnetic limiter currents. The DIII-D program was highlighted by the attainment of 11% beta with a double null divertor plasma. As for the fusion engineering research, development activities of the ceramic turbo-viscous pump and the surface insulation techniques for the tokamak in-vessel components are remarked in the vacuum technology area. In the high heat flux experiments with the JAERI Electron Beam Irradiation Stand (JEBIS), carbon-based materials and refractory metals were tested to evaluate surface erosion at plasma disruptions. The ITER Conceptual Design Activities, which began in April 1988 under the auspices of the IAEA, were successfully completed in December 1990. A lot of contributions to the program were made by JAERI people to support the design and R and D activities and to prepare a plan for the forthcoming Engineering Design Activities. (J.P.N.)

  15. Annual report of Naka Fusion Research Establishment for the period from April 1, 1992 to March 31, 1993

    International Nuclear Information System (INIS)

    Ohta, Mitsuru; Shimizu, Katsuhiro; Fujii, Tuneyuki; Nishi, Masataka; Matoba, Tohru; Kanazawa, Tetsuo

    1993-10-01

    Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1992 to March 31, 1993. The main objectives of JT-60U experiments in FY1992 were to improve plasma confinement properties and to study non-inductive current drive. High-βp H-mode performance obtained in March 1993 was highlighted, in particular, a world-record fusion-triple-product of 1.1 x 10 21 m -3 · s · keV, and record values for JT-60 of neutron yield rate of 5.6 x 10 16 s -1 , stored energy of 8.3 MJ, and H-factor of 3.6. The JFT-2M continued to study divertor biasing and ergodic limiter experiments, and disruption control by ECH. The study in Plasma Theory and Computation focused on scaling laws of the thermal energy confinement and the bootstrap current, the iron temperature gradient instability, the MHD stability, the rotation damping by external magnetic error field, and the burning plasma of D- 3 He fusion. As for the fusion engineering research, the vacuum technology advanced the development of a high resolution quadrupole mass spectrometer, etc. The super-conducting Demo Poloidal Coil achieved pulsed operation with 7 T in 0.5 s, and newly developed conductors made of Nb 3 Al and Nb 3 Sn showed 40 kA at 12 T and 82 kA at 13.6 T, respectively. A high energy H - beam of 350 kV, 0.17 A was produced with a current density of 10 mA/cm 2 . Much effort was made in developing the ECH gyrotron with an output power of 460 kW at 120 GHz for 100 ms. The main progress in the Tritium Systems Test Assembly (a US/Japan collaboration) was continuous loop run for 25 days. The developed plasma facing components posed no problem under a heat flux of 20 MW/m 2 for 30 s over 1000 thermal cycles. (J.P.N.)

  16. Annual report of the Naka Fusion Research Establishment for the period of April 1, 1987 to March 31, 1988

    International Nuclear Information System (INIS)

    1988-11-01

    Research and development activities of the Naka Fusion Research Establishment for the period of April 1987 to March 1988 are described. In JT-60, the plasma heating experiment aiming at a reactor-grade plasma was started in June 1987, after completing the integrated performance test of NBI and RF heating systems with the tokamak machine, most of the first wall being replaced to carbon tiles from titanium-carbide films. Enphasis was placed in the experiment on increasing the plasma current together with the optimization of plasma control and heating. The steady improvement of plasma performance lead finally in September reactor-grade plasma parameters, which were located inside the region depicted by the Atomic Energy Commission at the start of the JT-60 project. In JFT-2M and Doublet III-D, extensive experiments revealed detailed phenomenology of H-mode transition and its characteristics. The test of a prototype turbo molecular pump with a ceramic rotor driven by gas turbine was successfully completed. In the development of negative ion sources, steady improvement was made in the efficiency of negative ion formation and beam extraction. In the RF technology, test-fabricated 120 GHz gyrotron worked well. The Demo Poloidal Coil program was progressed as scheduled. The coils, two NbTi and one Nb 3 Sn, were under fabrication. The large cryogenic system was completed by sharing the JT-60 power supply. In the Tritium Process Laboratory, installation into glove boxes was completed in March 1988 of various experimental apparatus, i.e., fuel clean-up system, cryogenic distillation and thermal diffusion systsms for hydrogen isotope separation etc. In the reactor design study, recapitulation and review of FER design for last two years were made. (author)

  17. Annual report of the Naka Fusion Research Establishment for the period of April 1, 1986 to March 31, 1987

    International Nuclear Information System (INIS)

    1988-03-01

    Research and development activities of the Naka Fusion Research Establishment for the period of April 1986 to March 1987 are described. In JT-60 experiments, second phase experiments with Joule-heated plasma were performed in June and July 1986 and plasma discharge of n-barτ E = 3.1 x 10 -19 m -3 · sec with very low impurities was achieved in divertor configuration. Initial heating experiments in JT-60 were performed for August-November 1986 and January-March 1987. The highest central ion temperature in hydrogen discharge of 130 Million degrees, and plasma current drive by RF of 2 MA were achieved. The integrated performance tests of the NBI and RF heating systems of JT-60 were completed in July 1986, and the initial heating experiments were followed and finished in March 1987. The diagnostic system of JT-60 was successfully operated and produced large amount of valuable data. In Doublet III experiments, H-mode discharges with good confinement characteristics were achieved in divertor configurations. In JFT-2M non-circular plasma experiments remarkable results on H-mode discharge were achieved. As to studies on plasma-surface interaction, production of C 2 and C 3 compounds by chemical sputtering was confiremed and compared with the case of diamond-like surface. Data were accumurated for carbonization coating. A ceramic rotor driven by gas turbine was tested and successfully demonstrated continuous operation at 30,000 rpm in magnetic field. Development of 120 GHz Gyrotron was started focusing its objective to high power output. Experiments of IEA Large Coil Task were successfully carried out at ORNL. The demonstration poloidal coil program was progressed: Fablications of the coil and cryogenic system, and extention works of power supply from JT-60 proceeded. (author)

  18. Annual report of the Naka Fusion Research Establishment for the period of April 1 1989 to March 31 1990

    International Nuclear Information System (INIS)

    1990-09-01

    Research and development activities of the Naka Fusion Research Establishment for the period of April 1989 to March 1990 are reported. The experiment on JT-60 was continued to October 1989. In the pellet injection experiment, plasma energy confinement was improved and the maximum fusion product reached 1.2 x 10 20 m -3 s keV. The portion of the bootstrap current was up to 80% of the total plasma current in the high poloidal beta discharge. The fabrication of the new vacuum vessel and poloidal field coils for the JT-60 machine upgrade (JT-60U) have been made. The experiment to improve the confinement on JFT-2M was conducted. The ergodic magnetic limiter coils were installed. Quasi-steady-state H-mode discharge (10 sec at maximum) was achieved and a new high-beta regime with the improved Troyon coefficient have been explored in DIII-D. As for theoretical and computational studies, thermal instabilities of an edge plasma, plasma performance determined by the MHD instabilities and burning plasma problems were investigated. A new type of a vacuum pump--the ceramic turbo-viscous pump--has been developed. In the high heat flux technology, small-scale divertor samples are manufactured by means of brazing carbon fiber reinforced carbon composite to copper heat sinks. The thermal cycle tests show they endure against a heat flux up to 10MW/m 2 . As for the development of plasma heating technology, the 50 keV-10A negative hydrogen beam was extracted by means of seeding cesium in the ion plasma generator. 1.4 MW-10sec RF was generated from an improved electron gun in the modified 2GHz-range klystron. Nb 3 Sn superconducting coil with an inner diameter of 1.0 m was successfully magnetized up to 7 T in 1 sec. The gram-level tritium experiments were performed. Conceptual design of the International Thermonuclear Experimental Reactor (ITER) is proceeding under the auspices of the IAEA. Design study of the Fusion Experimental Reactor (FER) concept has been conducted. (J.P.N.)

  19. Annual report of Naka Fusion Research Establishment from April 1, 1999 to March 31, 2000

    International Nuclear Information System (INIS)

    Ninomiya, Hiromasa; Inabe, Teruo; Kaneko, Tadao; Konoshima, Sigeru; Miura, M. Yushi; Nakamura, Kazuyuki

    2001-01-01

    In JT-60, some mechanical improvements of the centrifugal pellet injector have been done for stable production and successive ejection of pellet. In addition, a guide tube for an injection from top of high-field side was installed as well as the low-field side in February 2000. The injection power of electron cyclotron heating (ECH) system of the frequency of 110 GHz installed last year was increased up to ∼0.75 MW for 2 seconds in this year using the control of RF beam angle. Two gyrotrons were newly installed with total power increased from 1 MW to 3 MW. Highlights of the JT-60 experiments in FY (Fiscal Year) 2000 may be summarized as follows: (1) A reversed shear discharge with an equivalent fusion multiplication factor Q DT eq of ∼0.5 was achieved successfully at plasma current of 2.4 MA for 0.8 seconds. (2) Quasi-steady operation of low current reversed shear plasma with a large fraction (∼80%) of bootstrap current was realized under full non-inductive current drive condition. H-factor of 3.3-3.8 at electron density as high as 73% of the Greenwald limit was sustained for 6 times of the energy confinement time. (3) Normalized beta exceeding the ideal no-wall stability limit was obtained in reversed shear plasmas with a ratio of an outer-wall radius to a plasma minor radius less than 1.3. (4) L-H transition power was reduced by ∼30% in the W-shaped divertor with pumping from both inside and outside slots compared with that in the open divertor. Helium exhaust rate in ELMy H-mode plasmas was improved up to 50% higher than the inside slot pumping. (5) Current drive efficiency of 1.3x10 19 A/m 2 /W was attained with the central electron temperature of 8.6 keV. The efficiency is about 2.6 times higher than that of 100 keV. On the JFT-2M, advanced and basic research of tokamak plasma is being produced including the application of the low activation ferritic steel. A dramatic reduction of trapped ion loss due to the toroidal field ripple was identified for the

  20. Annual report of Naka Fusion Research Establishment for the period from April 1, 1993 to March 31, 1994

    International Nuclear Information System (INIS)

    Matoba, Tohru; Nakamura, Yukiharu; Matsuzaki, Yoshimi; Araki, Masanori; Yamane, Yoshifumi

    1995-01-01

    Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1993 to March 31, 1994. The main objectives of JT-60U experiments in FY1993 were to achieve and sustain high confinement regime with current drive. The JFT-2M experiments progressed in the systematic study of the plasma responses by applying an external helical field and also in the study of the boundary plasma with electric field or current in the scrape off layer (SOL) introduced by the divertor bias system. The study in Plasma Theory and Computation focused on the ion temperature gradient instability, the linear toroidal particle simulation, the MHD stability and the analyses of burning plasma. The progresses on DIII-D experiments were obtained in the studies of divertor radiation, cryopumping and VH-mode plasma. As for the fusion engineering research, further developments of a ceramic vacuum pump and a high-resolution quadrupole mass spectrometer (QMS) were made. A high energy H - beam of 400keV and 0.18A was produced with a current density of 13mA/cm 2 for 1s. Many efforts were made in developing the long pulse gyrotron and the high efficiency collector potential depression (CPD) gyrotron in the radio-frequency (RF) technology area. The main progress in the Tritium Systems Test Assembly (under US/Japan collaboration) was to demonstrate the plasma exhaust stream under non-steady tokamak operation. Heating experiments of the development 1m long divertor module for ITER were performed at a heat flux of 15MW/m 2 for 30sec. The R and D of the reactor structure were focused on the major components such as non-circular bellows, fail-safe first wall, etc.. The R and D of the blanket technology were focussed on the box structure for ITER shielding blanket and the out-of-reactor testing of ITER breeding blanket. (J.P.N.)

  1. Annual report of Naka Fusion Research Establishment from April 1, 1999 to March 31, 2000

    Energy Technology Data Exchange (ETDEWEB)

    Ninomiya, Hiromasa; Inabe, Teruo; Kaneko, Tadao; Konoshima, Sigeru; Miura, M. Yushi; Nakamura, Kazuyuki [eds.] [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2001-01-01

    In JT-60, some mechanical improvements of the centrifugal pellet injector have been done for stable production and successive ejection of pellet. In addition, a guide tube for an injection from top of high-field side was installed as well as the low-field side in February 2000. The injection power of electron cyclotron heating (ECH) system of the frequency of 110 GHz installed last year was increased up to {approx}0.75 MW for 2 seconds in this year using the control of RF beam angle. Two gyrotrons were newly installed with total power increased from 1 MW to 3 MW. Highlights of the JT-60 experiments in FY (Fiscal Year) 2000 may be summarized as follows: (1) A reversed shear discharge with an equivalent fusion multiplication factor Q{sub DT}{sup eq} of {approx}0.5 was achieved successfully at plasma current of 2.4 MA for 0.8 seconds. (2) Quasi-steady operation of low current reversed shear plasma with a large fraction ({approx}80%) of bootstrap current was realized under full non-inductive current drive condition. H-factor of 3.3-3.8 at electron density as high as 73% of the Greenwald limit was sustained for 6 times of the energy confinement time. (3) Normalized beta exceeding the ideal no-wall stability limit was obtained in reversed shear plasmas with a ratio of an outer-wall radius to a plasma minor radius less than 1.3. (4) L-H transition power was reduced by {approx}30% in the W-shaped divertor with pumping from both inside and outside slots compared with that in the open divertor. Helium exhaust rate in ELMy H-mode plasmas was improved up to 50% higher than the inside slot pumping. (5) Current drive efficiency of 1.3x10{sup 19} A/m{sup 2}/W was attained with the central electron temperature of 8.6 keV. The efficiency is about 2.6 times higher than that of 100 keV. On the JFT-2M, advanced and basic research of tokamak plasma is being produced including the application of the low activation ferritic steel. A dramatic reduction of trapped ion loss due to the

  2. Annual report on major results and progress of Naka Fusion Research Establishment of JAERI from April 1 to September 30, 2005 and Fusion Research and Development Directorate of JAEA from October 1, 2005 to March 31, 2006

    International Nuclear Information System (INIS)

    Yoshida, Hidetoshi; Oasa, Kazumi; Hayashi, Takao; Nakamura, Hiroo; Ogawa, Hiroaki

    2006-09-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Naka Fusion Research Establishment of Japan Atomic Energy Research Institute (JAERI) during the period from April 1 to September 30, 2005 and at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from October 1, 2005 to March 31, 2006, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In JT-60, ferritic steel tiles (FSTs) were installed inside the vacuum vessel of JT-60U to reduce the toroidal field ripple. After the installation of FSTs, a high normalized beta plasma at β N ∼2.3 was sustained for 28.6s with ELMy H-mode confinement as required for an ITER hybrid operation scenario. National Centralized Tokamak was placed as the ITER satellite tokamak in collaboration with the EU fusion community, and the facility design was modified strongly in support of ITER. In theoretical and analytical researches, studies on H-mode confinement, ITB in reversed shear plasmas, aspect ratio effects on external MHD modes and magnetic island evolution in a rotating plasma were progressed. Progress was also made in the NEXT project in which the behaviors of collisionless MHD modes and the dynamics of zonal flows were simulated. 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 1000 s with 0.2 MW was demonstrated. Also current density of the neutral beam injector has been extended to 134A/m 2 at 0.75MeV. In the ITER Test Blanket Module (TBM), designs of Water and Helium Cooled Solid Breeder TBMs and R and Ds of tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets was also progressed. For the DEMO reactors, high temperature superconductor such as Bi2212 has been examined. In plasma facing

  3. Economics of fusion research

    International Nuclear Information System (INIS)

    1977-01-01

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

  4. 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.

  5. 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, *

  6. 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

  7. International fusion research council

    International Nuclear Information System (INIS)

    Belozerov, A.N.

    1977-01-01

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

  8. Fusion research in Hungary

    International Nuclear Information System (INIS)

    Zoletnik, S.

    2004-01-01

    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. ITER management advisory committee meeting in NAKA

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    1999-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held on 17 December 1999 in Naka, Japan. The main topics were the ITER EDA Status, Task Status Summary and Work Program and a schedule of ITER meetings

  10. Japanese fusion research

    International Nuclear Information System (INIS)

    Uchida, T.

    1987-01-01

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

  11. Bringing together fusion research

    International Nuclear Information System (INIS)

    Leiser, M.

    1982-01-01

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

  12. 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)

  13. International fusion research

    International Nuclear Information System (INIS)

    Pease, R.S.

    1983-01-01

    Nuclear energy of the light elements deuterium and lithium can be released if the 100 MK degree temperature required for deuterium-tritium thermonuclear fusion reactions can be achieved together with sufficient thermal insulation for a net energy yield. Progress of world-wide research shows good prospect for these physical conditions being achieved by the use of magnetic field confinement and of rapidly developing heating methods. Tokamak systems, alternative magnetic systems and inertial confinement progress are described. International co-operation features a number of bilateral agreements between countries: the Euratom collaboration which includes the Joint European Torus, a joint undertaking of eleven Western European nations of Euratom, established to build and operate a major confinement experiment; the development of co-operative projects within the OECD/IEA framework; the INTOR workshop, a world-wide study under IAEA auspices of the next major step in fusion research which might be built co-operatively; and assessments of the potential of nuclear fusion by the IAEA and the International Fusion Research Council. The INTOR (International Tokamak Reactor) studies have outlined a major plant of the tokamak type to study the engineering and technology of fusion reactor systems, which might be constructed on a world-wide basis to tackle and share the investment risks of the developments which lie ahead. This paper summarizes the recent progress of research on controlled nuclear fusion, featuring those areas where international co-operation has played an important part, and describes the various arrangements by which this international co-operation is facilitated. (author)

  14. Accelerator and fusion research division

    International Nuclear Information System (INIS)

    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

  15. Annual report of the Naka Fusion Research Establishment for the period of April 1 1988 to March 31 1989

    International Nuclear Information System (INIS)

    1989-08-01

    The experiment on JT-60 was resumed in May 1988 after the modification of the divertor configuration into a lower single-null type. An improved confinement associated with significant remote radiative cooling at the divertor region was obtained. In the confinement experiment on JFT-2M, an improved L mode was also obtained, in which density profile is peaked without edge pedestal in contrast to the H-mode confinement. A system test of a turbo molecular pump with a gas turbine-driven ceramic rotor successfully demonstrated a pumping speed. A 400 KW electron beam irradiation system was constructed for development of high heat flux components. The Large Coil Task, a ten-year long international collaboration under the auspices of the IEA, was successfully completed in January 1989. The International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activity was initiated under the auspices of the IAEA. (J.P.N.)

  16. Cold fusion research

    International Nuclear Information System (INIS)

    1989-11-01

    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

  17. Fusion research activities in China

    International Nuclear Information System (INIS)

    Deng Xiwen

    1998-01-01

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

  18. 50 years of fusion research

    Science.gov (United States)

    Meade, Dale

    2010-01-01

    Fusion energy research began in the early 1950s as scientists worked to harness the awesome power of the atom for peaceful purposes. There was early optimism for a quick solution for fusion energy as there had been for fission. However, this was soon tempered by reality as the difficulty of producing and confining fusion fuel at temperatures of 100 million °C in the laboratory was appreciated. Fusion research has followed two main paths—inertial confinement fusion and magnetic confinement fusion. Over the past 50 years, there has been remarkable progress with both approaches, and now each has a solid technical foundation that has led to the construction of major facilities that are aimed at demonstrating fusion energy producing plasmas.

  19. Controlled thermonuclear fusion: research on magnetic fusion

    International Nuclear Information System (INIS)

    Paris, P.J.

    1988-12-01

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

  20. Fusion research at Culham site

    International Nuclear Information System (INIS)

    Tolonen, P.; Toppila, T.

    1998-01-01

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

  1. Fusion research at ORNL

    International Nuclear Information System (INIS)

    1982-03-01

    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

  2. The current state of the development of the supercomputer system in plasma science and nuclear fusion research in the case of Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Azumi, Masafumi

    2004-01-01

    The progress of large scale scientific simulation environment in JAERI is briefly described. The expansion of fusion simulation science has been played a key role in the increasing performances of super computers and computer network system in JAERI. Both scalar parallel and vector parallel computer systems are now working at the Naka and Tokai sites respectively, and particle and fluid simulation codes developed under the fusion simulation project, NEXT, are running on each system. The storage grid system has been also successfully developed for effective visualization analysis by remote users. Fusion research is going to enter the new phase of ITER, and the need for the super computer system with higher performance are increasing more than as ever along with the development of reliable simulation models. (author)

  3. Fusion research at Imperial College

    International Nuclear Information System (INIS)

    Haines, M.G.

    1990-01-01

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

  4. Research into thermonuclear fusion

    International Nuclear Information System (INIS)

    Schumacher, U.

    1989-01-01

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

  5. Fusion research program in Korea

    International Nuclear Information System (INIS)

    Hwang, Y.S.

    1996-01-01

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

  6. Future directions in fusion research

    International Nuclear Information System (INIS)

    Clarke, J.F.

    1987-01-01

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

  7. (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.

  8. [Fusion energy research

    International Nuclear Information System (INIS)

    Phillips, C.A.

    1988-01-01

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

  9. Status report on fusion research

    International Nuclear Information System (INIS)

    Burkhart, Werner

    2005-01-01

    At the beginning of the twenty-first century mankind is faced with the serious problem of meeting the energy demands of a rapidly industrializing population around the globe. This, against the backdrop of fast diminishing fossil fuel resources (which have been the main source of energy of the last century) and the increasing realization that the use of fossil fuels has started to adversely affect our environment, has greatly intensified the quest for alternative energy sources. In this quest, fusion has the potential to play a very important role and we are today at the threshold of realizing net energy production from controlled fusion experiments. Fusion is, today, one of the most promising of all alternative energy sources because of the vast reserves of fuel, potentially lasting several thousands of years and the possibility of a relatively 'clean' form of energy, as required for use in concentrated urban industrial settings, with minimal long term environmental implications. The last decade and a half has seen unprecedented advances in controlled fusion experiments with the discovery of new regimes of operations in experiments, production of 16 MW of fusion power and operations close to and above the so-called 'break-even' conditions. A great deal of research has also been carried out in analysing various socio-economic aspects of fusion energy. This paper briefly reviews the various aspects and achievements of fusion research all over the world during this period

  10. New trends in fusion research

    CERN Multimedia

    CERN. Geneva

    2004-01-01

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

  11. Nuclear fusion research in Australia

    International Nuclear Information System (INIS)

    Cheetham, A.D.

    1997-01-01

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

  12. Collaborations in fusion research

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  13. Progress of laser fusion research

    International Nuclear Information System (INIS)

    Yamanaka, Chiyoe

    1988-01-01

    The history of the research on nuclear fusion utilizing laser is described. It started in USSR in 1968, but the full scale start of laser implosion nuclear fusion was in 1972. In Osaka University, nuclear fusion neutrons were detected with a solid deuterium target and the phenomenon of parametric abnormal absorption in laser plasma was found in 1971. The new type target for implosion nuclear fusion ''Canon ball'' was devised in 1975. The phenomenon of the abnormal transmission of laser beam through a thin metal film in a multiple film target was found in 1976, and named ''Osaka effect''. Also the development of lasers has been advanced, and in 1983, a largest glass laser in the world, Gekko 12, with 12 beams, 30 kJ output, 55 TW, was completed. The new target LHART was devised, which enabled the generation of 10 trillion D-T reaction neutrons. Due to the development of high power laser technology, the realization of the new design of fuel pellets, the evaluation of the data by computer simulation, and the realization of new plasma diagnostic method, the research on laser nuclear fusion has developed rapidly, and the attainment of break-even is expected in 1990s. The features of inertial nuclear fusion are enumerated. (Kako, I.)

  14. Fusion program research materials inventory

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  15. 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

  16. Research and development of fusion grid infrastructure based on atomic energy grid infrastructure (AEGIS)

    International Nuclear Information System (INIS)

    Suzuki, Y.; Nakajima, K.; Kushida, N.; Kino, C.; Aoyagi, T.; Nakajima, N.; Iba, K.; Hayashi, N.; Ozeki, T.; Totsuka, T.; Nakanishi, H.; Nagayama, Y.

    2008-01-01

    In collaboration with the Naka Fusion Institute of Japan Atomic Energy Agency (NFI/JAEA) and the National Institute for Fusion Science of National Institute of Natural Science (NIFS/NINS), Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) aims at establishing an integrated framework for experiments and analyses in nuclear fusion research based on the atomic energy grid infrastructure (AEGIS). AEGIS has been being developed by CCSE/JAEA aiming at providing the infrastructure that enables atomic energy researchers in remote locations to carry out R and D efficiently and collaboratively through the Internet. Toward establishing the integrated framework, we have been applying AEGIS to pre-existing three systems: experiment system, remote data acquisition system, and integrated analysis system. For the experiment system, the secure remote experiment system with JT-60 has been successfully accomplished. For the remote data acquisition system, it will be possible to equivalently operate experimental data obtained from LHD data acquisition and management system (LABCOM system) and JT-60 Data System. The integrated analysis system has been extended to the system executable in heterogeneous computers among institutes

  17. Proceedings of the workshop of three large tokamak cooperation on energy confinement scaling under intensive auxiliary heating, May 18 ∼ 20, 1992, Naka

    International Nuclear Information System (INIS)

    1992-09-01

    The workshop of three large tokamak cooperation W22 on 'Energy confinement scaling under intensive auxiliary heating' was held 18-20 May, 1992, at Naka Fusion Research Establishment. This proceedings compiles 14 synopses of contributions (5 from JET, 4 from JT-60, 3 from TFTR, and 1 each from DIII-D JFT-2M) and the summary of the workshop. Topic sections are ; (i) L-mode confinement and scaling, (ii) Confinement at high β P regimes, Supershots, High poloidal beta enhanced confinement mode etc., (iii) Confinement at various H-mode regimes and scaling (including the VH-mode), (iv) Characteristic time scales for present tokamak regimes, and (v) Theoretical comparison with experimental data. (author)

  18. Inertial fusion research: Annual technical report, 1985

    International Nuclear Information System (INIS)

    Larsen, J.T.; Terry, N.C.

    1986-03-01

    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

  19. Magnetic fusion research in developing countries

    International Nuclear Information System (INIS)

    Hassan, M.H.A.

    1990-01-01

    This article is a presentation prepared by the Third World Academy of Sciences on magnetic fusion research activity in the developing countries and its connection with the IAEA's own fusion programme. 6 figs, 1 tab

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  1. Muon-catalyzed fusion: A new direction in fusion research

    International Nuclear Information System (INIS)

    Jones, S.E.

    1986-01-01

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

  2. Muon-catalyzed fusion: a new direction in fusion research

    International Nuclear Information System (INIS)

    Jones, S.E.

    1986-01-01

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

  3. Fusion plasma research and education in Japan

    International Nuclear Information System (INIS)

    Inoue, N.

    1995-01-01

    Japanese fusion plasma research and education is reviewed by focusing on the activities promoted by the Ministry of Education, Science, Culture, and Sports (MOE). University fusion research is pursued by the academic interest and student education. A hierarchical structure of budget and manpower arrangement is observed. The small research groups of universities play the role of recruiting young students into the fusion and plasma society. After graduating the master course, most students are engaged by industries

  4. Survey of radioactive contamination distribution in the Naka-Dori area, Tohoku, Japan

    International Nuclear Information System (INIS)

    Hohara, Sin-ya; Inagaki, Masayo; Yamanishi, Hirokuni; Wakabayashi, Genichiro; Sugiyama, Wataru; Itoh, Tetsuo

    2013-01-01

    The Kinki University Atomic Energy Research Institute investigated radioactive contamination due to the Fukushima Daiichi Nuclear Power Plant accident in urban areas of the Fukushima Naka-Dori Area in the TOHOKU region, Japan. A specific activity measurement of the surface soil and a survey of the dose rate distribution in urban areas were performed. From the results of this research, a decrease in dose rate in paved areas became clear, and differences due to the “wash out effect” in paved areas for different paving materials was measured and verified. (author)

  5. West European magnetic confinement fusion research

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  6. Fusion energy research for ITER and beyond

    International Nuclear Information System (INIS)

    Romanelli, Francesco; Laxaaback, Martin

    2011-01-01

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

  7. Nuclear Fusion Fuel Cycle Research Perspectives

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  8. Research Needs for Magnetic Fusion Energy Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Neilson, Hutch

    2009-07-01

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

  9. Annual report of the Fusion Research Center for the period of April 1, 1982 to March 31, 1983

    International Nuclear Information System (INIS)

    1983-11-01

    Research and development activities of the Fusion Research Center (Department of Thermonuclear Fusion Research and Department of Large Tokamak Development) from April 1982 to March 1983 are described. The JFT-2 tokamak was shutdown after 10 years operation. Operation test of a new device JFT-2M was near completion. In the joint JAERI-USDOE experiment on Doublet-III a record value of beta, 4.6 %, was achieved. Major efforts in theory and computation was on high beta tokamak stability, second stability regions being found for low m internal modes. The JT-60 program progressed as scheduled, installation of the tokamak machine being initiated in February 1983. A 100 kV test was completed of prototype unit for JT-60 NBI. In the development of a high power klystron for JT-60 LH heating, a test fabricated tube generated 1 MW, 10 s RF pulses. Development of TiC coatings for JT-60 first wall was successfully concluded. In the superconducting magnet technology, the Japanese coil for IEA Large Coil Task was installed in a test facility at ORNL after successful performance test at Naka site. A 10 T experiment of a Nb 3 Sn coil with 60 cm inner bore was made. Construction of the Tritium Process Laboratory was started in February 1983. Design studies of the Fusion Experimental Reactor and INTOR were continued. (author)

  10. Cold fusion research in Italy

    International Nuclear Information System (INIS)

    Scaramuzzi, F.

    1993-01-01

    This paper summarizes cold fusion (CF) research in Italy. In Italy, many Agencies and Universities are moderately funding research in CF, and the scientists have made a few attempts to coordinate each other, organizing meetings and conferences. However, the activity has been mostly the fruit of the scientists' initiative, and never a coordinated proposal of Agencies and Universities. No position on the scientific validity of the subject has been officially taken and the funds for CF have been rather modest. The investments in Italy on CF, the figure referring to 1992 amounts to about 0.5 million dollars, not including expenses for personnel. A number of about 70 scientists, mostly working part-time, is committed all around the Country in research on CF. The lack of offical commitment and effective support by the Research Agencies and the Universities has not prevented scientists from being quite active in performing research. On the other side, it has to be acknowledged that no formal vetoes have been interposed to the free initiative of scientists in this field: on the contrary, some of the Agencies and Universities have moderately funded such an effort. The quality of the experiments in Italy has been increasingly good, and the results obtained are rather out standing in the general panorama of CF. But it is time to perform a more coordinated effort, keeping in mind that material science aspects, such as the characteristics of the materials used, play a very important role in the development of this topic. Thus, a much more intense effort is required to obtain a more substantial progress in the field. The increasingly convincing results obtained by the whole CF community, and the example of the Japanese Government and Industry, which appear to be determined to promoting CF research, have changed the panorama of CF. These are now signs that also the Italian scientific authorities could consider favouring research in this field in the near future. (J.P.N.)

  11. Atomic and Molecular Data Activities for Fusion Research in JAEA

    International Nuclear Information System (INIS)

    Nakano, T.

    2011-01-01

    The Japan Atomic Energy Agency (JAEA) has been producing, collecting and compiling cross-section data for atomic and molecular collisions and spectral data relevant to fusion research. In this talk, an overview of our activities since the last meeting in September 2009 will be presented. The state selective charge transfer cross-section data of Be 4+ , C 4+ and C 6+ by collision with H(n=2) in the collision energy range between 62 eV/amu and 6.2 keV/amu have been calculated with a molecular-bases close-coupling method. The calculated charge transfer data of C 4+ was implemented in a collisional-radiative model code for C 3+ , and it is shown that in some cases the charge transfer from C 4+ to H(n=2) populates predominantly C 3+ (n = 6, 7). The cross-section data of dissociative recombination and excitation of HD + , D 2+ , DT + , T 2+ 3 HeH + and 4 HeH + were produced by theoretical calculation. The principal quantum number of dissociated H atom isotopes was also given. The analytical expressions for the cross-section data for 26 processes of He-collision systems were produced in order to facilitate practical use of the data. The compiled data are in preparation for the web site at the URL of http://www-jt60.naka.jaea.go.jp/engish/JEAMDL/. The chemical sputtering yield data of CFC materials with hydrogen isotope collisions have been compiled. The ionization rate of W 44+ and the radiative and the dielectronic recombination rates of W 45+ were calculated with FAC. The ratio of these rates was compared with experimentally measured ratio of W 45+ density to W 44+ density in JT-60U, showing that the calculated ratio of the recombination ratio of W 45+ to the ionization rate of W 44+ is accurate within the experimental uncertainty (∼ 30%). The atomic and molecular data activities in JAEA are pursued in collaboration with Japanese universities, and other department of JAEA. (author)

  12. Heavy-Ion Fusion Accelerator Research, 1991

    International Nuclear Information System (INIS)

    1992-03-01

    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

  13. The development of laser fusion research

    International Nuclear Information System (INIS)

    Mima, Kunioki

    1998-01-01

    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)

  14. The development of laser fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Mima, Kunioki [Osaka Univ., Suita (Japan). Inst. of Laser Engineering

    1998-11-01

    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)

  15. The growth of European fusion research

    International Nuclear Information System (INIS)

    Palumbo, D.

    1988-01-01

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

  16. Stellarator fusion neutronics research in Australia

    International Nuclear Information System (INIS)

    Zimin, S.; Cross, R.C.

    1997-01-01

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

  17. Iodine laser for fusion research

    International Nuclear Information System (INIS)

    Dance, B.

    1988-01-01

    The most powerful iodine laser in the world, known as Asterix IV, is being prepared for operation at The Max Plank-Institut fuer Quantenoptik at Garching, near Munich, in West Germany. It is expected to produce 2kJ pulses of 1ns duration. Shorter pulses of about 200 ps duration should be obtainable at power levels of over 5 TW. Pulses of maximum power will be available every 20 minutes; this frequency is expected to be adequate for fusion experiments, although the short rate could be raised if necessary by greater gas circulation and cooling. (Author)

  18. Heavy-ion fusion accelerator research, 1989

    International Nuclear Information System (INIS)

    1990-06-01

    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

  19. Trends in fusion reactor safety research

    International Nuclear Information System (INIS)

    Herring, J.S.; Holland, D.F.; Piet, S.J.

    1991-01-01

    Fusion has the potential to be an attractive energy source. From the safety and environmental perspective, fusion must avoid concerns about catastrophic accidents and unsolvable waste disposal. In addition, fusion must achieve an acceptable level of risk from operational accidents that result in public exposure and economic loss. Finally, fusion reactors must control routine radioactive effluent, particularly tritium. Major progress in achieving this potential rests on development of low-activation materials or alternative fuels. The safety and performance of various material choices and fuels for commercial fusion reactors can be investigated relatively inexpensively through reactor design studies. These studies bring together experts in a wide range of backgrounds and force the group to either agree on a reactor design or identify areas for further study. Fusion reactors will be complex with distributed radioactive inventories. The next generation of experiments will be critical in demonstrating that acceptable levels of safe operation can be achieved. These machines will use materials which are available today and for which a large database exists (e.g. for 316 stainless steel). Researchers have developed a good understanding of the risks associated with operation of these devices. Specifically, consequences from coolant system failures, loss of vacuum events, tritium releases, and liquid metal reactions have been studied. Recent studies go beyond next step designs and investigate commercial reactor concerns including tritium release and liquid metal reactions. 18 refs

  20. Magnetic confinement fusion energy research

    International Nuclear Information System (INIS)

    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 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

  1. Annual report of the Fusion Research and Development Center for the period of April 1, 1980 to March 31, 1981

    International Nuclear Information System (INIS)

    1982-03-01

    Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1980 to 1981 are described. In plasma physics research, 1.5 MW NBI heating experiments were successfully made on JFT-2 to yield an average beta value of 2.5% without any deleterious effect on plasma confinement. Joint JAERI-US/DOE ECRH experiments revealed detailed physics of plasma heating. Installation of a 1 MW ICRF system was completed. In the Doublet-III experiment, a JAERI-US/DOE cooperation program, extensive studies were made on Joule heated dee-shaped Plasmas. In theory and computation emphasis was placed on beta optimization of tokamaks. Construction of JT-60 was continued as planned. Manufacturing of the major components and facilities was advanced well, e.g. 14 out of the 19 toroidal field coils were completed. Construction of the buildings was continued at the Naka site. In plasma heating technology, construction of the JT-60 prototype NBI unit was in progress, and development works on ion sources and beam line components as well. Trial fabrication of high power klystrons for JT-60 RF heating was started. In superconducting magnet technology, cool-down tests of cluster coils were successfully made. Manufacturing of the Japanese coil for the Large Coil Task under the auspiece of IEA, and of a Nb 3 Sn test module coil was continued. A test facility for the LCT coil was completed. Basic studies on key processes of tritium technology were continued using hydrogen and deuterium. Design of the Tritium Process Laboratory was continued. Development of first wall materials for JT-60 was advanced. Extensive tests were made on a number of low-Z coatings. Design studies of INTOR, a cooperative work in IAEA, were continued. In addition, design of the Fusion Experimental Reactor was started on a conventional type tokamak reactor and swimming pool type one. (author)

  2. Computer applications in controlled fusion research

    International Nuclear Information System (INIS)

    Killeen, J.

    1975-02-01

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

  3. Progress of laser nuclear fusion research

    International Nuclear Information System (INIS)

    Shiraga, Hiroyuki

    2017-01-01

    This paper describes the principle and features of nuclear fusion using laser, as well as its basic concepts such as high-temperature / high-density implosion system and fast ignition of fuel. At present, researches aiming at nuclear fusion ignition have been developing. As the current state of researches, this paper reviews the situations of FIREX (Fast Ignition Realization Experiment) project of Japan focusing on direct irradiation implosion and fast ignition system, as well as NIF (National Ignition Facility) project of the U.S. aiming at ignition combustion based on indirect irradiation implosion and central ignition system. In collaboration with the National Institute for Fusion Science, Osaka University started FIREX-1 project in 2003. It built a heating laser LFEX of 10 kJ/1 to 10ps, and started an implosion/heating integration experiment in 2009. Currently, it is developing experiment to achieve heating to 5 keV. At NIF, the self-heating of central sparks via energy of α particles generated in the nuclear fusion reaction has been realized. This paper also overviews R and D issues surrounding the lasers for reactors for use in laser nuclear fusion power generators. (A.O.)

  4. Vacuum engineering for fusion research and fusion reactors

    International Nuclear Information System (INIS)

    Pittenger, L.C.

    1976-01-01

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

  5. Portuguese research program on nuclear fusion

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  6. 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

  7. Maryland controlled fusion research program

    International Nuclear Information System (INIS)

    Griem, H.R.; Liu, C.S.

    1992-01-01

    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

  8. Current state of nuclear fusion research

    International Nuclear Information System (INIS)

    Naraghi, M.

    1985-01-01

    During the past quarter century, plasma physics and nuclear fusion research have gone through impressive development. Tokamak, is realized to be the number one candidate for nuclear fusion reactor. Two large experiments, one called Joint European Torus (JET) at Culham, England, and the other JT-60 project in Japan have been completed and have reported preliminary results. In JET an average electron density of 4x10 13 pcls/ cm 3 , ion temperatures of 3Kev and energy confinement of 0.8 sec have been achieved. However, the Zeff has been even equal to 10 which unfortunately is a source of plasma energy loss. JT-60 has not offered any appreciable results yet, however, the objectives and initial tests promise long pulse duration, with very high ion and plasma densities. Both experiments have promised to achieve conditions approaching those needed in a fusion reactor. Other important experiments will be discussed and the role of third world countries will be emphasized. (Author)

  9. Belgian research on fusion beryllium waste

    International Nuclear Information System (INIS)

    Druyts, F.; Mallants, D.; Sillen, X.; Iseghem, P. Van

    2004-01-01

    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)

  10. 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...

  11. 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...

  12. Computer applications in controlled fusion research

    International Nuclear Information System (INIS)

    Killeen, J.

    1975-01-01

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

  13. The JET project and the European fusion research programme

    International Nuclear Information System (INIS)

    Wuester, H.-O.

    1984-01-01

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

  14. 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.

  15. 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.

  16. Accelerator ampersand Fusion Research Division 1991 summary of activities

    International Nuclear Information System (INIS)

    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

  17. 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.

  18. Overview of materials research for fusion reactors

    International Nuclear Information System (INIS)

    Muroga, T.; Gasparotto, M.; Zinkle, S.J.

    2002-01-01

    Materials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Emphasis is placed on programs and strategies for developing blanket structural materials, and recent highlights in research and development for reduced activation ferritic martensitic steels, vanadium alloys and SiC/SiC composites, and in mechanistic experimental and modeling studies. The common critical issue for the candidate materials is the effect of irradiation with helium production. For the qualification of materials up to the full lifetime of a DEMO and Power Plant reactors, an intense neutron source with relevant fusion neutron spectra is crucial. Elaborate use of the presently available irradiation devices will facilitate efficient and sound materials development within the required time scale

  19. The history of controlled fusion research

    International Nuclear Information System (INIS)

    Trocheris, M.

    1980-01-01

    The idea of using nuclear reaction between light elements to produce energy for peaceful objectives originated towards the mid-forties. In this work, the author traces the various stages of reserach undertaken in this field from the first fusion experiments to the projects now in course of production. Research scientists have travelled a long, hard road to reach a new development phase during which technological problems will play a prominent part [fr

  20. Accelerator and Fusion Research Division 1989 summary of activities

    International Nuclear Information System (INIS)

    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

  1. 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.

  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. Overview of US heavy ion fusion research

    International Nuclear Information System (INIS)

    Logan, G.; Bieniosek, F.; Celata, C.; Henestroza, E.; Kwan, J.; Lee, E.P.; Leitner, M.; Prost, L.; Roy, P.; Seidl, P.A.; Eylon, S.; Vay, J.-L.; Waldron, W.; Yu, S.; Barnard, J.; Callahan, D.; Cohen, R.; Friedman, A.; Grote, D.; Kireeff Covo, M.; Meier, W.R.; Molvik, A.; Lund, S.; Davidson, R.; Efthimion, P.; Gilson, E.; Grisham, L.; Kaganovich, I.; Qin, H.; Startsev, E.; Rose, D.; Welch, D.; Olson, C.; Kishek, R.; O'Shea, P.; Haber, I.

    2005-01-01

    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)

  4. Overview of US heavy ion fusion research

    International Nuclear Information System (INIS)

    Logan, B.G.; Bieniosek, F.M.; Celata, C.M.; Henestroza, E.; Kwan, J.W.; Lee, E.P.; Leitner, M.; Roy, P.K.; Seidl, P.A.; Eylon, S.; Vay, J-L.; Waldron, W.L.; Yu, S.S.; Barnard, J.J.; Callahan, D.A.; Cohen, R.H.; Friedman, A.; Grote, D.P; Covo, Kireeff M.; Meier, W.R.; Molvik, A.W.; Lund, S.M.; Davidson, R.C.; Efthimion, P.C.; Gilson, E.P.; Grisham, L.R.; Kaganovich, I.D.; Qin, H.; Startsev, E.A.; Rose, D.V.; Welch, D.R.; Olson, C.L.; Kishek, R.A.; O'Shea, P.; Haber, I.; Prost, L.R.; Prost, L.

    2004-01-01

    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

  5. Fusion reactor materials research in China

    International Nuclear Information System (INIS)

    Qian Jiapu

    1994-10-01

    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, Li 2 O, γ-LiAlO 2 ) 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

  6. New approaches to the economic evaluation of fusion research

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  7. American research programs on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    At a time when the site of the European JET project has been decided, this study proposes to highlight the American effort in this field over the last five years. The Federal Civil Research and Development budget assigned to Energy has been multiplied by 6.3 and inside this budget the portion allocated to fusion has been multiplied by a factor of 6, in value. Two avenues have been explored; magnetic confinement and inertial confinement but one reaction only has been considered, namely D + T fusion. In magnetic confinement, the first operational reactor is being contemplated for around the year 2012. Three technologies have been explored in inertial confinement: by laser beams, electron beams and ion beams [fr

  8. Maryland controlled fusion research program. Volume I

    International Nuclear Information System (INIS)

    1985-01-01

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

  9. Review of fusion research program: historical summary and program projections

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, E.S.

    1976-09-01

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

  10. Nuclear fusion research at Tokamak Energy Ltd

    International Nuclear Information System (INIS)

    Windridge, Melanie J.; Gryaznevich, Mikhail; Kingham, David

    2017-01-01

    Tokamak Energy's approach is close to the mainstream of nuclear fusion, and chooses a spherical tokamak, which is an economically developed form of Tokamak reactor design, as research subjects together with a high-temperature superconducting magnet. In the theoretical prediction, it is said that spherical tokamak can make tokamak reactor's scale compact compared with ITER or DEMO. The dependence of fusion energy multiplication factor on reactor size is small. According to model studies, it has been found that the center coil can be protected from heat and radiation damage even if the neutron shielding is optimized to 35 cm instead of 1 m. As a small tokamak with a high-temperature superconducting magnet, ST25 HTS, it demonstrated in 2015 continuous operation for more than 24 hours as a world record. Currently, this company is constructing a slightly larger ST40 type, and it is scheduled to start operation in 2017. ST40 is designed to demonstrate that it can realize a high magnetic field with a compact size and aims at attaining 8-10 keV (reaching the nuclear fusion reaction temperature at about 100 million degrees). This company will verify the startup and heating technology by the coalescence of spherical tokamak expected to have plasma current of 2 MA, and will also use 2 MW of neutral particle beam heating. In parallel with ST40, it is promoting a development program for high-temperature superconducting magnet. (A.O.)

  11. LLL magnetic fusion research: the first 25 years

    International Nuclear Information System (INIS)

    Post, R.F.

    1978-01-01

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

  12. State of controlled nuclear fusion research

    International Nuclear Information System (INIS)

    Rodrigo, A.B.

    1978-04-01

    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) [es

  13. Virtual laboratory for fusion research in Japan

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  14. Trends of researches for fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Ozawa, Yasutomo; Enoto, Takeaki

    1975-01-01

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

  15. Customizable scientific web portal for fusion research

    International Nuclear Information System (INIS)

    Abla, G.; Kim, E.N.; Schissel, D.P.; Flanagan, S.M.

    2010-01-01

    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

  16. Customizable scientific web portal for fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Abla, G., E-mail: abla@fusion.gat.co [General Atomics, P.O. Box 85608, San Diego, CA (United States); Kim, E.N.; Schissel, D.P.; Flanagan, S.M. [General Atomics, P.O. Box 85608, San Diego, CA (United States)

    2010-07-15

    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

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

    International Nuclear Information System (INIS)

    1980-08-01

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

  18. 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)

  19. Fusion research in the European Community

    International Nuclear Information System (INIS)

    Wolf, G.H.

    1988-01-01

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

  20. IAEA and IEA roles in international fusion energy research

    International Nuclear Information System (INIS)

    Dolan, T.; Nakamura, K.

    2000-01-01

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

  1. Present status of nuclear fusion research and development

    International Nuclear Information System (INIS)

    Discussions are included on the following topics: (1) plasma confinement theoretical research, (2) torus plasma research, (3) plasma measurement research, (4) technical development of equipment, (5) plasma heating, (6) vacuum wall surface phenomena, (7) critical plasma test equipment design, (8) noncircular cross-sectional torus test equipment design, (9) nuclear fusion reactor design, (10) nuclear fusion reactor engineering, (11) summary of nuclear fusion research in foreign countries, and (12) long range plan in Japan

  2. Induction linacs for heavy ion fusion research

    International Nuclear Information System (INIS)

    Fessenden, T.J.; Avery, R.T.; Brady, V.; Bisognano, J.; Celata, C.; Chupp, W.W.; Faltens, A.; Hartwig, E.C.; Judd, D.L.; Keefe, D.; Kim, C.H.; Laslett, L.J.; Lee, E.P.; Rosenblum, S.S.; Smith, L.; Warwick, A.

    1984-01-01

    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 proportional70 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. (orig.)

  3. 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.

  4. Heavy-ion accelerator research for inertial fusion

    International Nuclear Information System (INIS)

    1987-08-01

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

  5. Research on an Agricultural Knowledge Fusion Method for Big Data

    Directory of Open Access Journals (Sweden)

    Nengfu Xie

    2015-05-01

    Full Text Available The object of our research is to develop an ontology-based agricultural knowledge fusion method that can be used as a comprehensive basis on which to solve agricultural information inconsistencies, analyze data, and discover new knowledge. A recent survey has provided a detailed comparison of various fusion methods used with Deep Web data (Li, 2013. In this paper, we propose an effective agricultural ontology-based knowledge fusion method by leveraging recent advances in data fusion, such as the semantic web and big data technologies, that will enhance the identification and fusion of new and existing data sets to make big data analytics more possible. We provide a detailed fusion method that includes agricultural ontology building, fusion rule construction, an evaluation module, etc. Empirical results show that this knowledge fusion method is useful for knowledge discovery.

  6. 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....

  7. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    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. The authors 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

  8. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    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

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

    International Nuclear Information System (INIS)

    Isei, Nobuaki

    2011-03-01

    Research Center, preliminary technological development on R and D issues related to each of low-activation structural materials, SiC/SiC composite materials, tritium technologies, advanced tritium breeder, and advanced neutron multiplier to create DEMO reactors was conducted. In addition, review of conceptual design of DEMO reactors through cooperation with universities and domestic research institutes, and that of selection of the models of super computers to be installed in the Fusion Computer Simulation Center were promoted. In engineering demonstration/design activities for the International Fusion Materials Irradiation Facility (IFMIF), the development of lithium test loop was promoted under cooperation with JAEA's Oarai Research and Development Center which has technologies for liquid metals, and the local construction was started. Besides, design of accelerators was promoted and fabrication of prototypes was started. Concerning activities related to Satellite Tokamak (JT-60SA), integrated design of JT-60SA was completed in Japan and Europe incorporating domestic opinions, and fabrication of superconducting conductors for poloidal field coils was started and procurement activities were promoted in the facilities for fabricating superconducting conductors constructed in Naka Fusion Institute. At the same time, the operation of JT-60 was completed in August 2008 aiming for the establishment of JT-60SA, and preparations for dismantling toward full-scale dismantling and removal are being promoted according to schedule. In addition, the development of the Rokkasho BA site, which will be the center of the BA activities, was also advanced according to schedule, and construction of the DEMO R and D Building, the Computer Simulation and Remote experiment Building, and the IFMIF/EVEDA Accelerator Building, and the central substation was completed as originally planned in March 2010. For research and development on fusion plasma, research on the realization of steady-state and

  10. Software problems in magnetic fusion research

    International Nuclear Information System (INIS)

    Gruber, R.

    1982-01-01

    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.)

  11. Major achievements and challenges of fusion research

    International Nuclear Information System (INIS)

    Tendler, Michael

    2015-01-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

    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

  13. Comparative assessment of world research efforts on magnetic confinement fusion

    International Nuclear Information System (INIS)

    McKenney, B.L.; McGrain, M.; Rutherford, P.H.

    1990-02-01

    This report presents a comparative assessment of the world's four major research efforts on magnetic confinement fusion, including a comparison of the capabilities in the Soviet Union, the European Community (Western Europe), Japan, and the United States. A comparative evaluation is provided in six areas: tokamak confinement; alternate confinement approaches; plasma technology and engineering; and fusion computations. The panel members are involved actively in fusion-related research, and have extensive experience in previous assessments and reviews of the world's four major fusion programs. Although the world's four major fusion efforts are roughly comparable in overall capabilities, two conclusions of this report are inescapable. First, the Soviet fusion effort is presently the weakest of the four programs in most areas of the assessment. Second, if present trends continue, the United States, once unambiguously the world leader in fusion research, will soon lose its position of leadership to the West European and Japanese fusion programs. Indeed, before the middle 1990s, the upgraded large-tokamak facilities, JT-60U (Japan) and JET (Western Europe), are likely to explore plasma conditions and operating regimes well beyond the capabilities of the TFTR tokamak (United States). In addition, if present trends continue in the areas of fusion nuclear technology and materials, and plasma technology and materials, and plasma technology development, the capabilities of Japan and Western Europe in these areas (both with regard to test facilities and fusion-specific industrial capabilities) will surpass those of the United States by a substantial margin before the middle 1990s

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

    International Nuclear Information System (INIS)

    Lechon, Y.; Saez, R.; Cabal, H.

    2003-01-01

    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)

  15. 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.

  16. Annual report for FY 2010 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2010 - March 31, 2011

    International Nuclear Information System (INIS)

    2012-03-01

    This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The research and development activities obtained certain results in the fields of operational radiation protection technique and the construction of calibration fields for neutron beams. The institutes in Tokai, Takasaki, Aomori and Naka were suffered from the Great East Japan Earthquake and the nuclear power plant accident which followed the earthquake. (author)

  17. International information exchange in fusion research

    International Nuclear Information System (INIS)

    Strickler, C.S.

    1979-01-01

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

  18. Plasma physics and controlled nuclear fusion research

    International Nuclear Information System (INIS)

    1980-01-01

    Full text: During the last decade, growing efforts have been devoted to studying the possible forms an electricity-producing thermonuclear reactor might take and the various technical problems that will have to be overcome. Previous IAEA Conferences took place in Salzburg (1961), Culham (1965), Novosibirsk (1968), Madison (1971), Tokyo (1974), Berchtesgaden (1976) and Innsbruck (1978) The exchange of information that has characterized this series of meetings is an important example of international co-operation and has contributed substantially to progress in controlled fusion research. The results of experiments in major research establishments, as well as the growing scientific insights in the field of plasma physics, give hope that the realization of nuclear fusion will be made possible on a larger scale and beyond the laboratory stage by the end of this century. The increase of the duration of existing tokamak discharges requires solution of the impurity control problem. First results from the new big machines equipped with the poloidal divertor recently came into operation. PDX (USA) and ASDEX (F.R. of Germany) show that various divertor configurations can be established and maintained and that the divertors function in the predicted manner. The reduction of high-Z impurities on these machines by a factor 10 was achieved. As a result of extensive research on radio-frequency (RF) plasma heating on tokamaks: PLT (USA), TFR (France), JFT-2 (Japan), the efficiency of this attractive method of plasma heating comparable to neutral beam heating was demonstrated. It was shown that the density of the input power of about 5-10 kW/cm 2 is achievable and this limit is high enough for application to reactor-like machines. One of the inspiring results reported at the conference was the achievement of value (the ratio of plasma pressure to magnetic field pressure) of ∼ 3% on tokamaks T-11 (USSR) and ISX-B (USA). It is important to note that this value exceeds the

  19. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    Miyahara, Akira; Yamamoto, Mitsuyoshi.

    1976-01-01

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

  20. Experiences with remote collaborations in fusion research

    International Nuclear Information System (INIS)

    Wurden, G.A.; Davis, S.; Barnes, D.

    1998-03-01

    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

  1. Fusion Ignition Research Experiment System Integration

    International Nuclear Information System (INIS)

    Brown, T.

    1999-01-01

    The FIRE (Fusion Ignition Research Experiment) configuration has been designed to meet the physics objectives and subsystem requirements in an arrangement that allows remote maintenance of in-vessel components and hands-on maintenance of components outside the TF (toroidal-field) boundary. The general arrangement consists of sixteen wedged-shaped TF coils that surround a free-standing central solenoid (CS), a double-wall vacuum vessel and internal plasma-facing components. A center tie rod is used to help support the vertical magnetic loads and a compression ring is used to maintain wedge pressure in the inboard corners of the TF coils. The magnets are liquid nitrogen cooled and the entire device is surrounded by a thermal enclosure. The double-wall vacuum vessel integrates cooling and shielding in a shape that maximizes shielding of ex-vessel components. The FIRE configuration development and integration process has evolved from an early stage of concept selection to a higher level of machine definition and component details. This paper describes the status of the configuration development and the integration of the major subsystem components

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

    International Nuclear Information System (INIS)

    Post, R.F.

    1980-01-01

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

  3. Radiological safety design considerations for fusion research experiments

    International Nuclear Information System (INIS)

    Crase, K.W.; Singh, M.S.

    1979-01-01

    A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

  4. 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.

  5. Role of supercomputers in magnetic fusion and energy research programs

    International Nuclear Information System (INIS)

    Killeen, J.

    1985-06-01

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

  6. Advanced laser fusion target fabrication research and development proposal

    International Nuclear Information System (INIS)

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

    1979-05-01

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

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

    International Nuclear Information System (INIS)

    Lehnert, Bo

    2001-06-01

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

  8. Customizable Scientific Web Portal for Fusion Research

    Energy Technology Data Exchange (ETDEWEB)

    Abla, G; Kim, E; Schissel, D; Flannagan, S [General Atomics, San Diego (United States)

    2009-07-01

    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

  9. Customisable Scientific Web Portal for Fusion Research

    Energy Technology Data Exchange (ETDEWEB)

    Abla, G; Kim, E; Schissel, D; Flannagan, S [General Atomics, San Diego (United States)

    2009-07-01

    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

  10. Finnish Fusion Research Programme Yearbook 1993-1994

    International Nuclear Information System (INIS)

    Karttunen, S.; Paettikangas, T.

    1995-05-01

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

  11. 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)

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

    International Nuclear Information System (INIS)

    1984-08-01

    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

  13. Fusion research and technology records in INIS database

    International Nuclear Information System (INIS)

    Hillebrand, C.D.

    1998-01-01

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

  14. Japanese program of materials research for fusion reactors

    International Nuclear Information System (INIS)

    Hasiguti, R.R.

    1982-01-01

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

  15. 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.

  16. The European Fusion Energy Research Programme towards the realization of a fusion demonstration reactor

    International Nuclear Information System (INIS)

    Gasparotto, M.; Laesser, R.

    2006-01-01

    Since its inception, the European Fusion Programme has been orientated towards the establishment of the knowledge base needed for the definition of a reactor to be used for power production. Its ultimate goal is then to demonstrate the scientific and the technological feasibility of fusion power while incorporating the assessment of the safety, environmental, social and economic features of this type of energy source. At present, the JET device, the largest tokamak in the world, and the other medium-sized experimental machines are contributing essentially to the basic scientific phase of this development path. Their successful operation greatly contributed to support the design basis of ITER, the next step in fusion, which will aim to demonstrate the scientific and technical feasibility of fusion power production by achieving extended D-T burning plasma operation. Following ITER, the conception and construction of the DEMO device is planned. DEMO will be a demonstration power plant which will be the first fusion device to generate a significant amount of electrical power from fusion. This paper describes the status of fusion research and the European strategy for achievement of the ultimate goal of construction of a prototype reactor. (author)

  17. 1981 inertial fusion research annual technical report

    International Nuclear Information System (INIS)

    Solomon, D.E.; Wei, J.L.; Greacen, N.T.

    1981-01-01

    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

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

    International Nuclear Information System (INIS)

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

    2001-03-01

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

  19. Magnetic fusion energy research and development

    International Nuclear Information System (INIS)

    1984-02-01

    This report on the Department of Energy's Magnetic Fusion Program was requested by the Secretary of Energy. The Panel finds that substantial progress has been made in the three years since the previous ERAB review, although budget constraints have precluded the engineering initiatives recommended in that review and authorized in the Magnetic Fusion Energy Engineering Act of 1980 (the Act). Recognizing that the goals of the Act cannot now be met, the Panel recommends that the engineering phase be further postponed in favor of a strong base program in physics and technology, including immediate commitment to a major new tokamak-based device for the investigation of an ignited long-pulse plasma designated in this report as the Burning Core Experiment or BCX. Resources to design such a device could be obtained from within the existing program by redirecting work toward to BCX. At this time it is not possible to assess accurately the potential economic viability of fusion power in the future. The Panel strongly recommends expansion of international collaboration, particularly the joint construction and operation of major new unique facilities, such as the proposed BCX

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

    International Nuclear Information System (INIS)

    1983-01-01

    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

  1. Institute for Fusion Research and Large Helical Device program

    International Nuclear Information System (INIS)

    Iiyoshi, Atsuo

    1989-01-01

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

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  3. The technology benefits of inertial confinement fusion research

    International Nuclear Information System (INIS)

    Powell, H.T.

    1999-01-01

    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 6 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

  4. Fusion plasma physics research on the H-1 national facility

    International Nuclear Information System (INIS)

    Harris, J.

    1998-01-01

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

  5. Fusion Research Center, theory program. Progress report

    International Nuclear Information System (INIS)

    1982-01-01

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

  6. Heavy Ion Fusion Accelerator Research (HIFAR)

    International Nuclear Information System (INIS)

    1991-04-01

    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 C s + 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

  7. Pulsed power particle beam fusion research

    International Nuclear Information System (INIS)

    Yonas, G.

    1979-01-01

    Although substantial progress has been made in the last few years in developing the technology of intense particle beam drivers, there are still several unanswered questions which will determine their ultimate feasibility as fusion ignition systems. The questions of efficiency, cost, and single pulse scalability appear to have been answered affirmatively but repetitive pulse technology is still in its infancy. The allowable relatively low pellet gains and high available beam energies should greatly ease questions of pellet implosion physics. Insofar as beam-target coupling is concerned, ion deposition is thought to be understood and our measurements of enhanced electron deposition agree with theory. With the development of plasma discharges for intense beam transport and concentration it appears that light ion beams will be the preferred approach for reactors

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  9. Outline of research project on nuclear fusion, 1985

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1985-08-01

    When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, and develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interactions 2) science and engineering of tritium, and influence on living things, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal year 1984 of each research are outlined. (J.P.N.)

  10. Outline of research project on nuclear fusion, 1984

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1984-08-01

    When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, a nd develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interaction, 2) science and engineering of tritium and influence on living things, 3) fundamentals of core control, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal 1983 of each research are outlined. (J.P.N.)

  11. Summaries of special research project on nuclear fusion 1980

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1981-09-01

    This is a report of the research project entitled ''Nuclear fusion'', supported by the grant in aid for fusion research from the Ministry of Education in the fiscal year 1980. The research project was started in April, 1980, and comprises the following seventeen subjects of nuclear fusion research. 1) Heavy irradiation effects, 2) plasma-wall interaction, 3) neutronics, 4) welding engineering, 5) science and technology of tritium, 6) biological effects of tritium, 7) diagnostics of high temperature plasma, 8) new lasers, 9) fundamentals of plasma heating, 10) high efficiency energy conversion, 11) theory and computer simulation, 12) superconducting materials, 13) fundamental phenomena of superconductivity, 14) magnet technology, 15) heat transfer and structural engineering, 16) system design, and 17) resources and assessment of fusion energy. 43 summaries concerning reactor materials and plasma-wall interaction, 29 summaries concerning the science, technology and biological effects of tritium, 41 summaries concerning the fundamentals of reactor plasma control, 15 summaries concerning the technology of superconducting magnets, and 14 summaries concerning the design of fusion reactors and its evaluation are collected in this report, and their results and progress can be known. (Kako, I.)

  12. 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)

    1994-09-01

    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.)

  13. Centralized supercomputer support for magnetic fusion energy research

    International Nuclear Information System (INIS)

    Fuss, D.; Tull, G.G.

    1984-01-01

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

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

    International Nuclear Information System (INIS)

    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

  15. 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.

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

    International Nuclear Information System (INIS)

    Itoh, Sanae

    1993-07-01

    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)

  17. Progress in heavy ion fusion research

    International Nuclear Information System (INIS)

    Celata, C.M.; Bieniosek, F.M.; Henestroza, E.; Kwan, J.W.; Lee, E.P.; Logan, G.; Prost, L.; Seidl, P.A.; Vay, J.-L.; Waldron, W.L.; Yu, S.S.; Barnard, J.J.; Callahan, D.A.; Cohen, R.H.; Friedman, A.; Grote, D.P.; Lund, S.M.; Molvik, A.; Sharp, W.M.; Westenskow, G.

    2003-01-01

    The U.S. Heavy Ion Fusion program has recently commissioned several new experiments. In the High Current Experiment [P. A. Seidl et al., Laser Part. Beams 20, 435 (2003)], a single low-energy beam with driver-scale charge-per-unit-length and space-charge potential is being used to study the limits to transportable current posed by nonlinear fields and secondary atoms, ions, and electrons. The Neutralized Transport Experiment similarly employs a low-energy beam with driver-scale perveance to study final focus of high perveance beams and neutralization for transport in the target chamber. Other scaled experiments--the University of Maryland Electron Ring [P. G. O'Shea et al., accepted for publication in Laser Part. Beams] and the Paul Trap Simulator Experiment [R. C. Davidson, H. Qin, and G. Shvets, Phys. Plasmas 7, 1020 (2000)]--will provide fundamental physics results on processes with longer scale lengths. An experiment to test a new injector concept is also in the design stage. This paper will describe the goals and status of these experiments, as well as progress in theory and simulation. A proposed future proof-of-principle experiment, the Integrated Beam Experiment, will also be described

  18. Physics Regimes in the Fusion Ignition Research Experiment (FIRE)

    International Nuclear Information System (INIS)

    D.M. Meade; S.C.Jardin; C.E. Kessel; M.A. Ulrickson; J.H. Schultz; P.H. Rutherford; J.A. Schmidt; J.C. Wesley; K.M. Young; N.A.Uckan; R.J. Thome; P. Heitzenroeder; B.E. Nelson; and C.C.Baker

    2001-01-01

    Burning plasma science is recognized widely as the next frontier in fusion research. The Fusion Ignition Research Experiment (FIRE) is a design study of a next-step burning plasma experiment with the goal of developing a concept for an experimental facility to explore and understand the strong nonlinear coupling among confinement, magnetohydrodynamic (MHD) self-heating, stability, edge physics, and wave-particle interactions that is fundamental to fusion plasma behavior. This will require plasmas dominated by alpha heating (Q greater than or equal to 5) that are sustained for a duration comparable to characteristic plasma timescales (greater than or equal to 10) tau(subscript ''E''), approximately 4 tau(subscript ''He''), approximately 2 tau(subscript ''skin''). The work reported here has been undertaken with the objective of finding the minimum size (cost) device to achieve these physics goals

  19. Status and development plan of nuclear fusion research in the US

    International Nuclear Information System (INIS)

    Kang Weihong

    2012-01-01

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

  20. ITER implementation and fusion energy research in China

    International Nuclear Information System (INIS)

    Zhao, Jing; Feng, Zhaoliang; Yang, Changchun

    2015-01-01

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

  1. Achievements and challenges in particle beam fusion research

    International Nuclear Information System (INIS)

    Yonas, G.

    1978-01-01

    Recent developments in particle beam fusion research, as well as critical issues which remain to be solved are summarized. Until now primary emphasis has been on driver development, but as sources have increased in energy output and intensity and diagnostic techniques have improved, implosion studies have been initiated

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

    International Nuclear Information System (INIS)

    Wendt, Amy; Callis, Richard; Efthimion, Philip; Foster, John; Keane, Christopher; Onsager, Terry; O'Shea, Patrick

    2015-01-01

    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

  3. 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

  4. Fusion research as a subject of parliamentary technology assessment

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1975-01-01

    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.)

  6. New heavy-ion-fusion accelerator research program

    International Nuclear Information System (INIS)

    Herrmannsfeldt, W.B.

    1983-05-01

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

  7. Fusion research and third world countries

    International Nuclear Information System (INIS)

    El Nadi, A.M.

    1987-01-01

    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.) [pt

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

    International Nuclear Information System (INIS)

    Tosato, G.C.

    2002-01-01

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

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

    International Nuclear Information System (INIS)

    Tosato, G.C.

    2003-01-01

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

  10. Present status of fusion researches in USA, 4

    International Nuclear Information System (INIS)

    Yoshikawa, Shoichi; Okabayashi, Michio

    1983-01-01

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

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

    International Nuclear Information System (INIS)

    1982-02-01

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

  12. Interfacing between concrete and steel construction and fusion research devices

    International Nuclear Information System (INIS)

    Willoughby, E.

    1981-01-01

    In 1976 Giffels Associates, Inc. an architect/engineer organization, was retained by the United States Department of Energy to provide Title I and Title II design services and Title III construction inspection services for the Tokamak Fusion Test Reactor now being installed at the Princeton Plasma Physics Laboratory in Princeton, New Jersey. Construction of the complex required to house and serve the reactor itself, designed by others, now commencing. During building construction several problems occurred with respect to the interface between the building design, construction and the fusion device (reactor). A brief description of some of these problems and related factors is presented, which may be of benefit to those persons active in continuing fusion research and experimental work

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

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1980-08-01

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

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

    International Nuclear Information System (INIS)

    Okano, Kunihiko; Kurihara, Kenichi; Tobita, Kenji

    2006-01-01

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

  15. Je otylost (obezita) nakažlivá?

    Czech Academy of Sciences Publication Activity Database

    Čechová, Dana

    2001-01-01

    Roč. 66, č. 2 (2001), s. 152-153 ISSN 0366-0486 R&D Projects: GA ČR GV524/96/K162 Institutional research plan: CEZ:AV0Z5052915 Keywords : obesity * adenovirus Ad-36 Subject RIV: FQ - Public Health Care, Social Medicine

  16. 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)

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

    International Nuclear Information System (INIS)

    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

  18. Research into controlled fusion in tokamaks

    International Nuclear Information System (INIS)

    Zacek, F.

    1992-01-01

    During the thirty years of tokamak research, physicists have been approaching step by step the reactor breakeven condition defined by the Lawson criterion. JET, the European Community tokamak is probably the first candidate among the world largest tokamaks to reach the ignition threshold and thus to demonstrate the physical feasibility of thermonuclear reaction. The record plasma parameters achieved in JET at H plasma modes due to powerful additional plasma heating and due to substantial reduction of plasma impurities, opened the door to the first experiment with a deuterium-tritium plasma. In the paper, the conditions and results of these tritium experiments are described in detail. The prospects of the world tokamak research and of the participation of Czechoslovak physicists are also discussed. (J.U.) 3 figs., 6 refs

  19. Inertial fusion research. Annual technical report, 1984

    International Nuclear Information System (INIS)

    Larsen, J.T.; Terry, N.C.

    1985-03-01

    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

  20. The Swedish fusion research programme on magnetic confinement 1978

    International Nuclear Information System (INIS)

    Lehnert, B.

    1978-02-01

    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)

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

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    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

  2. 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

  3. Atomic data for controlled fusion research

    International Nuclear Information System (INIS)

    Barnett, C.F.; Ray, J.A.; Ricci, E.; Wilker, M.I.; McDaniel, E.W.; Thomas, E.W.; Gilbody, H.B.

    1977-02-01

    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

  4. Status of cold fusion research in Japan

    International Nuclear Information System (INIS)

    Kitamura, Akira

    2015-01-01

    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

  5. 1978 annual report on laser fusion research

    International Nuclear Information System (INIS)

    Johnson, R.R.

    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

  6. Progress in toroidal confinement and fusion research

    International Nuclear Information System (INIS)

    Furth, H.P.

    1987-10-01

    During the past 30 years, the characteristic T/sub i/n tau/sub E/-value of toroidal-confinement experiments has advanced by more than seven orders of magnitude. Part of this advance has been due to an increase of gross machine parameters. Most of this advance has been due to an increase of gross machine parameters. Most of the advance is associated with improvements in the ''quality of plasma confinement.'' The combined evidence of spherator and tokamak research clarifies the role of magnetic-field geometry in determining confinement and points to the importance of shielding out plasma edge effects. A true physical understanding of anomalous transport remains to be achieved. 39 refs., 11 figs., 1 tab

  7. Heavy-Ion Fusion Accelerator Research, 1992

    International Nuclear Information System (INIS)

    1993-06-01

    The National Energy Strategy calls for a demonstration IFE power plant by the year 2025. The cornerstone of the plan to meet this ambitious goal is research and development for heavy-ion driver technology. A series of successes indicates that the technology being studied by the HIFAR Group -- the induction accelerator -- is a prime candidate for further technology development toward this long-range goal. The HIFAR program addresses the generation of high-power, high-brightness beams of heavy ions; the understanding of the scaling laws that apply in this hitherto little-explored physics regime; and the validation of new, potentially more economical accelerator strategies. Key specific elements to be addressed include: fundamental physical limits of transverse and longitudinal beam quality; development of induction modules for accelerators, along with multiple-beam hardware, at reasonable cost; acceleration of multiple beams, merging of the beams, and amplification of current without significant dilution of beam quality; final bunching, transport, and focusing onto a small target. In 1992, the HIFAR Program was concerned principally with the next step toward a driver: the design of ILSE, the Induction Linac Systems Experiments. ILSE will address most of the remaining beam-control and beam-manipulation issues at partial driver scale. A few parameters -- most importantly, the line charge density and consequently the size of the ILSE beams -- will be at full driver scale. A theory group closely integrated with the experimental groups continues supporting present-day work and looking ahead toward larger experiments and the eventual driver. Highlights of this long-range, driver-oriented research included continued investigations of longitudinal instability and some new insights into scaled experiments with which the authors might examine hard-to-calculate beam-dynamics phenomena

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

    International Nuclear Information System (INIS)

    1981-01-01

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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  10. Maryland magnetic fusion research program: MS speromak

    International Nuclear Information System (INIS)

    DeSilva, A.W.; Goldenbaum, G.C.; Griem, H.R.

    1989-07-01

    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

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

    International Nuclear Information System (INIS)

    Henline, P.; Giarrusso, J.; Davis, S.; Casper, T.

    1993-01-01

    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

  12. 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.

  13. Heavy-ion fusion accelerator research in the USA

    International Nuclear Information System (INIS)

    Bangerter, R.O.; Godlove, T.D.; Herrmannsfeldt, W.B.; Keefe, D.

    1985-01-01

    In October 1983, a Heavy-Ion Fusion Accelerator Research programme (HIFAR) was established under the Office of Energy Research of the United States Department of Energy. The programme goal over the next several years is to establish a data base in accelerator physics and technology that can allow the potential of heavy ion fusion to be accurately assessed. Three new developments have taken place in the HIFAR programme. First, a decision has been made to concentrate the experimental programme on the development of multiple-beam induction linacs. Second, new beam transport experiments over a large number of quadrupole elements show that stable beam propagation occurs for significantly higher beam currents than had been believed possible a few years ago. Third, design calculations now show that a test accelerator of modest size and cost can come within a factor of three of testing almost all of the physics and technical issues appropriate to a power plant driver. (author)

  14. Overview of FAR-TECH's magnetic fusion energy research

    Science.gov (United States)

    Kim, Jin-Soo; Bogatu, I. N.; Galkin, S. A.; Spencer, J. Andrew; Svidzinski, V. A.; Zhao, L.

    2017-10-01

    FAR-TECH, Inc. has been working on magnetic fusion energy research over two-decades. During the years, we have developed unique approaches to help understanding the physics, and resolving issues in magnetic fusion energy. The specific areas of work have been in modeling RF waves in plasmas, MHD modeling and mode-identification, and nano-particle plasma jet and its application to disruption mitigation. Our research highlights in recent years will be presented with examples, specifically, developments of FullWave (Full Wave RF code), PMARS (Parallelized MARS code), and HEM (Hybrid ElectroMagnetic code). In addition, nano-particle plasma-jet (NPPJ) and its application for disruption mitigation will be presented. Work is supported by the U.S. DOE SBIR program.

  15. Development of laser technology in Research Center of Laser Fusion

    International Nuclear Information System (INIS)

    Zheng Wanguo; Deng Ying; Zhou Wei

    2013-01-01

    This paper reviews the progress in the construction of SG-Ⅲ laser facility, integrated Testbed and XG-Ⅲ laser facility and that in the upgrade of the prototype of SG-Ⅲ, and the development in assembling and installing technology, and the achievements in maintaining cleanliness project and metrology in Laser Fusion Research Center, China Academy of Engineering Physics in China in 2012. (authors)

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

    International Nuclear Information System (INIS)

    1991-01-01

    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

  17. Trends of plasma physics and nuclear fusion research life cycle and research effort curve

    International Nuclear Information System (INIS)

    Ohe, Takeru; Kanada, Yasumasa; Momota, Hiromu; Ichikawa, Y.H.

    1979-05-01

    This paper presents a quantitative analysis of research trends in the fields of plasma physics and nuclear fusion. This analysis is based on information retrieval from available data bases such as INSPEC tapes. The results indicate that plasma physics research is now in the maturation phase of its life cycle, and that nuclear fusion research is in its growth phase. This paper indicates that there is a correlation between the number of accumulated papers in the fields of plasma physics and nuclear fusion and the experimentally attained values of the plasma ignition parameter ntT. Using this correlation ''research effort curve'', we forecast that the scientific feasibility of controlled fusion using magnetic confinement systems will be proved around 1983. (author)

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

    International Nuclear Information System (INIS)

    Deng, X.W.

    1990-01-01

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

  19. Be Bold : An Alternative Plan for Fusion Research

    Energy Technology Data Exchange (ETDEWEB)

    Wurden, Glen Anthony [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-06-15

    Government sponsored magnetic fusion energy research in the USA has been on downward trajectory since the early 1990’s. The present path is unsustainable. Indeed, our research community and national research facilities are withering from old-age and lack of investment. The present product (tokamak-centric production of electricity) does not yet work, will not be economic, and is clearly not valued or needed by our society. Even if a prototype existed at any cost, DT-based fusion energy would come too late to significantly impact the reduction of CO2 emissions in this century. This white paper outlines what “being bold” could mean with respect to the invention and application of nuclear fusion technologies, and how the USA could once again set a visionary example for the world. I present the discussion in two parts, reflecting on the NAS panel two-part assignment of a plan “with” and “without” ITER.

  20. Fusion research in the UK 1945-1960

    International Nuclear Information System (INIS)

    Hendry, J.; Lawson, J.D.

    1993-01-01

    Two workers, involved in the research programmes themselves, document the developments in fusion research in the United Kingdom from 1945 until 1960. Started as part of the official history of the United Kingdom Atomic Energy Authority, the text is drawn from work by various teams of scientists at laboratories around the United Kingdom. This previewing of the research programmes lead to an inevitable evaluation of their worth, an assessment of their political implications and speculation on whether certain changes might have advanced scientific progress more readily. (U.K.)

  1. Mission and design of the Fusion Ignition Research Experiment (FIRE)

    International Nuclear Information System (INIS)

    Meade, D.M.; Jardin, S.C.; Schmidt, J.

    2001-01-01

    Experiments are needed to test and extend present understanding of confinement, macroscopic stability, alpha-driven instabilities, and particle/power exhaust in plasmas dominated by alpha heating. A key issue is to what extent pressure profile evolution driven by strong alpha heating will act to self-organize advanced configurations with large bootstrap current fractions and internal transport barriers. A design study of a Fusion Ignition Research Experiment (FIRE) is underway to assess near term opportunities for advancing the scientific understanding of self-heated fusion plasmas. The emphasis is on understanding the behavior of fusion plasmas dominated by alpha heating (Q≥5) that are sustained for durations comparable to the characteristic plasma time scales (≥20 τ E and ∼τ skin , where τ skin is the time for the plasma current profile to redistribute at fixed current). The programmatic mission of FIRE is to attain, explore, understand and optimize alpha-dominated plasmas to provide knowledge for the design of attractive magnetic fusion energy systems. The programmatic strategy is to access the alpha-heating-dominated regime with confidence using the present advanced tokamak data base (e.g., Elmy-H-mode, ≤0.75 Greenwald density) while maintaining the flexibility for accessing and exploring other advanced tokamak modes (e. g., reversed shear, pellet enhanced performance) at lower magnetic fields and fusion power for longer durations in later stages of the experimental program. A major goal is to develop a design concept that could meet these physics objectives with a construction cost in the range of $1B. (author)

  2. 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

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

    International Nuclear Information System (INIS)

    Karttunen, S.; Heikkinen, J.; Korhonen, R.

    1998-01-01

    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

  4. Research programme on controlled thermonuclear fusion - Synthesis report 2008

    International Nuclear Information System (INIS)

    Werthmueller, A.

    2009-06-01

    Switzerland is associated to the International Thermonuclear Experimental Reactor (ITER) project carried out in the framework of the European Atomic Energy Community (EURATOM). The current stage includes on-site civil engineering works. The Variable Configuration Tokamak (TCV) of the 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL will remain an important recognized research facility until the start of the ITER operation foreseen in 2018. At the European level, the whole fusion research is coordinated and partly financed by the Joint Undertaking Fusion for Energy (JU F4E). The large flexibility of the TCV design and operation modus allow the creation and control of plasmas of various shapes, what is a very useful option to verify the results of numerical simulations. Besides, the hyper-frequency power density injected into the plasma is the highest ever recorded in the world. Research topics studied with the TCV include the stationary regimes in the tokamaks; a plasma current of more than 70 kA could be maintained, what represents an improvement by a factor of 3 to 4 of the confinement quality. For the first time in the world a configuration of the 'snowflake' type could be created and the power density on the wall of the vacuum chamber could be reduced accordingly. Numerical models allowed the analysis of turbulence and heat transport, of the magneto-hydrodynamic stability of the tokamaks and stellarators as well as the optimization of the magnetic confinement. Results concerning the so-called 'saw teeth' instability were experimentally confirmed on the Joint European Torus (JET). Theoretical researches were carried out on the fluctuations, turbulence and transport phenomena in the magnetized toric plasmas. At the Paul Scherrer Institute (PSI) the effect of the fast neutrons emitted by the fusion reactions on the walls of the fusion reactors was investigated. Irradiation simulations were carried out by means of the Swiss Spallation Neutron Source

  5. Surface study of fusion research in universities linkage organization

    International Nuclear Information System (INIS)

    Miyahara, Akira.

    1980-04-01

    The surface studies for nuclear fusion research consist of the studies on the surface process and the surface damage. The problems with the surface study are different at different research stages. The plasma-wall interaction in the ignition stage is mainly concerned with heating. The impurity control becomes important in the breakeven stage. In the longer burn experiment, the problems of plasma contamination and ash accumulation are serious, and the blistering is also a problem. From the reactor aspect, the reduction of life of wall due to the irradiation of high fluence must be considered. The surface damage due to plasma disruption is a very big problem. The activities concerning the surface studies in university-linked organizations are the surface characterization for fusion reactor materials by low energy ion scattering spectroscopy, the high power ion irradiation test for CTR first wall, data compilation on plasma-wall interaction, the studies of sputtering process and surface coating, and the study on hydrogen isotope permeation through metals for fusion reactors. Other activities such as the sample characterization at many universities using the SUS 304 samples from the same lot, and the collaboration works on JIPP-T-2 plasma wall experiments are introduced. Concerning the surface study, US-Japan or international collaboration are strongly expected. (Kato, T.)

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  7. Accelerator and Fusion Research Division. Annual report, October 1977--September 1978

    Energy Technology Data Exchange (ETDEWEB)

    1979-04-01

    Research is reported for the combined groups consisting of the Accelerator Division and the Magnetic Fusion Energy Group. Major topics reported include accelerator operations, magnetic fusion energy, and advanced accelerator development. (GHT)

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

    International Nuclear Information System (INIS)

    2016-12-01

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

  9. Research and Application of Autodesk Fusion360 in Industrial Design

    Science.gov (United States)

    Song, P. P.; Qi, Y. M.; Cai, D. C.

    2018-05-01

    In 2016, Fusion 360, a productintroduced byAutodesk and integrating industrial design, structural design, mechanical simulation, and CAM, turns out a design platform supportingcollaboration and sharing both cross-platform and via the cloud. In previous products, design and manufacturing use to be isolated. In the course of design, research and development, the communication between designers and engineers used to go on through different software products, tool commands, and even industry terms. Moreover, difficulty also lies with the communication between design thoughts and machining strategies. Naturally, a difficult product design and R & D process would trigger a noticeable gap between the design model and the actual product. A complete product development process tends to cover several major areas, such as industrial design, mechanical design, rendering and animation, computer aided emulation (CAE), and computer aided manufacturing (CAM). Fusion 360, a perfect design solving the technical problems of cross-platform data exchange, realizes the effective control of cross-regional collaboration and presents an overview of collaboration and breaks the barriers between art and manufacturing, andblocks between design and processing. The “Eco-development of Fusion360 Industrial Chain” is both a significant means to and an inevitable trend forthe manufacturers and industrial designers to carry out innovation in China.

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

    International Nuclear Information System (INIS)

    Conn, R.W.; Berkner, K.H.; Culler, F.L.; Davidson, R.C.; Dreyfus, D.A.; Holdren, J.P.; McCrory, R.L.; Parker, R.R.; Rosenbluth, M.N.; Siemon, R.E.; Staudhammer, P.; Weitzner, H.

    1992-09-01

    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)

  11. Research program. Controlled thermonuclear fusion. Synthesis report 2015

    International Nuclear Information System (INIS)

    Villard, L.; Marot, L.; Soom, P.

    2016-01-01

    In 1961, 3 years after the 2 nd International Conference on Peaceful Use of Nuclear Energy, the Research Centre on Plasma Physics (CRPP) was created as a department of the Federal Institute of Technology (EPFL) in Lausanne (Switzerland). From 1979, CRPP collaborates to the European Program on fusion research in the framework of EURATOM. In 2015 its name was changed to Swiss Plasma Centre (SPC). The advantages of fusion are remarkable: the fuel is available in great quantity all over the world; the reactor is intrinsically safe; the reactor material, activated during operation, loses practically all its activity within about 100 years. But the working up of the controlled fusion necessitates extreme technological conditions. In 1979, the Joint European Torus (JET) began its operation; today it is still the most powerful tokamak in the world, in which an energy yield Q of 0.65 could be obtained. In 2015, the stellarator Wendelstein 7-X (W7X), the largest in the world, was set into operation. The progress realized in the framework of EURATOM has led to the planning of the experimental reactor ITER which is being built at Cadarache (France). ITER is designed to reach a Q-value largely above 1. The future prototype reactor DEMO is foreseen in 2040-2050. It should demonstrate the ability of a fusion reactor to inject permanently electricity into the grid. In 2015, SPC participated in the works on ITER in the framework of the Fusion for Energy (F4E) agency. At EPFL the research concerns the physics of the magnetic confinement with experiments on the tokamak TCV (variable configuration tokamak), the numerical simulations, the plasma heating and the generation of current by hyper frequency radio waves. At the Paul Scherrer Institute (PSI), research is devoted to the superconductivity; at the Basel University the studies get on interactions between the plasma and the tokamak walls. The large flexibility of TCV allows creating and controlling plasmas of different shapes which

  12. Research program. Controlled thermonuclear fusion. Synthesis report 2013

    International Nuclear Information System (INIS)

    Villard, L.; Marot, L.

    2014-01-01

    In 1961, 3 years after the 2 nd International Conference on Peaceful Use of Nuclear Energy, the Research Centre on Plasma Physics (CRPP) was created as a department of the Federal Institute of Technology (EPFL) in Lausanne (Switzerland). From 1979, CRPP collaborates to the European Program on fusion research in the framework of EURATOM. The advantages of fusion are remarkable: the fuel is available in great quantity all over the world; the reactor is intrinsically safe; the reactor material, activated during operation, loses practically all its activity within about 100 years. But the working up of the controlled fusion necessitates extreme technological conditions. The progress realized in the framework of EURATOM has led to the design of the experimental reactor ITER which is being built at Cadarache (France). The future prototype reactor DEMO is foreseen in 2040-2050. In 2013, CRPP participated in the works on ITER in the framework of the Fusion for Energy (F4E) agency. At EPFL the research concerns the physics of the magnetic confinement with experiments on the tokamak TCV (variable configuration tokamak), the numerical simulations, the plasma heating and the generation of current by hyper frequency radio waves. At the Paul Scherrer Institute (PSI), research is devoted to the superconductivity. At the Basel University the studies get on interactions between the plasma and the tokamak walls. A new improved confinement regime, called IN-mode, was discovered on TCV. The theory and numerical simulation group interprets the experimental results and foresees those of futures machines. It requires very high performance computers. The Gyrotron group develops radiofrequency sources in the mm range for heating the TCV plasma as well as for ITER and the Wendelstein-7 stellarator. Concerning superconductivity, tests are conducted at PSI on toroidal cables of ITER. The development of conductors and coils for the DEMO reactor has been pursued. In the context of international

  13. Data management in a fusion energy research experiment

    International Nuclear Information System (INIS)

    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

  14. Magnetohydrodynamic research in fusion blanket engineering and metallurgical processing

    International Nuclear Information System (INIS)

    Tokuhiro, A.

    1991-11-01

    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

  15. The heavy ion fusion research program in West Germany

    International Nuclear Information System (INIS)

    Bock, R.

    1984-01-01

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

  16. Synthetic report 2012. Research programme on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2013-01-01

    Since 1961, Switzerland participates in the research on thermonuclear fusion thanks to the creation of the Research Centre in Plasma Physics. In 1979 it entered into partnership with the European programme on fusion through its adhesion to EURATOM. The thermonuclear fusion is an interesting energy source because the basic fuel is practically inexhaustible and its use does not release any significant CO 2 quantity and very little radioactive residues. But its working up faces enormous physical and technological difficulties. The International Thermonuclear Reactor (ITER), presently in construction, has to demonstrate the technological feasibility of the controlled fusion. Il will be followed by DEMO, foreseen for 2040-2050, which must guarantee the economical rentability. At CRPP the research projects are partitioned onto several sites: at the Swiss Federal Institute of Technology (EPFL) in Lausanne, they concern the physics of the magnetic confinement with the Variable Geometry Tokamak (TCV), the development of theoretical models and the numerical simulation, the plasma heating and the generation of hyper frequency waves; the Paul Scherrer Institute (PSI) studies the superconductivity and the materials; the interactions between the plasma and the Tokamak walls are studied at the Basel University for the structures of ITER. Thanks to its large flexibility, TCV allows the creation and the control of plasmas of very different forms. The injection system of millimetric waves allows orienting the injected power according to specific profiles. By using the asymmetry of the flow in the toroidal sense, the plasma rotation could be measured with a much better accuracy than before. In TCV, by playing on the form of the plasma, it was possible to strongly reduce the energy quantity which is expelled by the Edge Localized Modes (ELM) onto the wall of the vacuum chamber. The ‘snowflake’ configuration created in TCV allows distributing the ELM energy onto several impact

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

    International Nuclear Information System (INIS)

    1977-02-01

    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.)

  18. Research programme on controlled thermonuclear fusion. Synthesis report 2011

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2012-01-01

    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), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. 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. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma internal relaxation

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

    International Nuclear Information System (INIS)

    Kasada, Ryuta; Goto, Takuya; Miyazawa, Junichi; Fujioka, Shinsuke; Hiwatari, Ryoji; Oyama, Naoyuki; Tanigawa, Hiroyasu

    2013-01-01

    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.)

  20. Public acceptance of fusion energy and scientific feasibility of a fusion reactor. Spin-off effects of fusion research and development

    International Nuclear Information System (INIS)

    Morino, Nobuyuki; Ogawa, Yuichi

    1998-01-01

    It is observed that new and sophisticated technologies developed through research and development in relation to magnetic confinement fusion have been transferred to other industrial and scientific fields with remarkable spin-off effects. Approximately 10 years ago, the Japan Atomic Industrial Forum (JAIF) has investigated technical transfer and spin-off effects of fusion technologies developed in Japan. The essence of the results of this investigation as well as high technologies developed in the last decade, some of which are in the early stage of technical spin-off, are described. It is additionally explained that independent technical development conducted by our country as well as by engineers themselves is important in achieving effective spin-off. An outline of scientific spin-off effects is also described, including utilization technologies of fusion reactions besides those for energy production purposes, the progress of scientific understanding in the course of fusion research, and scientific information transfer and communication with other fields. (author)

  1. Research program. Controlled thermonuclear fusion. Synthesis report 2014

    International Nuclear Information System (INIS)

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

    2015-01-01

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

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

    International Nuclear Information System (INIS)

    1989-01-01

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

  3. H-1NF: Australian national fusion plasma research facility

    International Nuclear Information System (INIS)

    Blackwell, B.D.; Borg, G.G.; Dewar, R.L.; Howard, J.; Gardner, H.J.; Rudakov, D.L.; Sharp, L.E.; Shats, M.G.; Warr, G.B.

    1997-01-01

    The H-1 heliac is a helical axis stellarator of moderate size and novel, flexible configuration. Since commissioning, H-1 has operated in quasi-continuous mode at low magnetic field. For higher fields ≤1T an ECRH heating system (28GHz, 200kW) has been installed under a collaborative agreement between ANU and NIFS. H-1 has recently been promoted to national facility status (H-1NF), which will include upgrades of the rf and ech heating systems to megawatt powers, and power supply and diagnostic and data system enhancements. This facilitates collaborative research locally (through the Australian Fusion Research Group consortium) and internationally. Results of a number of basic experiments in quasi-continuous mode are presented. (author)

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  5. Socioeconomic Research on Fusion. Serf 1997-98

    International Nuclear Information System (INIS)

    Saez, R.; Lechon, Y.; Cabal, H.; Lomba, L.; Palomino, I.; Recreo, F.; Robles, B.; Suanez, A.; Cancio, D.

    1999-01-01

    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

  6. Status of light ion inertial fusion research at NRL

    International Nuclear Information System (INIS)

    Cooperstein, G.; Barker, R.J.; Colombant, D.G.; Goldstein, S.A.; Meger, R.A.; Mosher, D.; Neri, J.M.; Ottinger, P.F.

    1984-01-01

    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/cm 2 . Includes 6 diagrams

  7. 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)

  8. [Research progress in hirudin fusion protein--review].

    Science.gov (United States)

    Zhang, Chuan-Ling; Yu, Ai-Ping; Jin, Ji-De; Wu, Chu-Tse

    2007-02-01

    Natural hirudin extracted from the secretion of medical leech salivary gland is a single-chain peptide containing 65 aminoacid residues with molecular weight of 7000 D, and exists in three isomers of HV1, HV2 and HV3. Hirudin possesses three disulfide bridges forming the structure of core cyclic peptides, which binds to the catalytic site of thrombin so as to inhibit the catalysis of thrombin. Its c-terminus rich in acidic aminoacid residues possesses hydrophilicity, and is free on the molecular surface, and can bind with fibrin recognition site of hirudin. The minimal segment of 12 - 16 C-terminal acidic residues keeps the minimal activity of anti-thrombosis. Thus, hirudin, as a potent and specific inhibitor of thrombin, can be used to protect from and to treat clinically thrombosis. As it has some disadvantages such as short half-life, bleeding side-effect and mono-function, and so on, hirudin has been fused with some other functional proteins in recent years. The obtained fusion proteins can prolong the half life of hirudin, or relieve it bleeding side effect, or bring new functions, such as thrombolysis, inhibiting the platelet aggregation, targeting specifically. The research progress in hirudin fusion protein was summarized in this review.

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

    International Nuclear Information System (INIS)

    PROJECT STAFF

    2001-01-01

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

  10. Superconducting magnet and conductor research activities in the US fusion program

    International Nuclear Information System (INIS)

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

    2006-01-01

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

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

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2011-01-01

    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

  12. The role of atomic and molecular processes in fusion research

    International Nuclear Information System (INIS)

    Harrison, M.F.A.

    1977-01-01

    This paper considers the relevance of atomic and molecular processes to research into controlled nuclear fusion and in particular their effects upon the magnetically confined plasma in Tokamak experiments and conceptual Tokamak reactors. The relative significance of collective phenomena and of single particle collisions to both plasma heating and loss processes are discussed and the pertinent principles of plasma refuelling and plasma diagnostics are outlined. The methods by which atomic and molecular data are applied to these problems, the contributing effects of surface interactions and the consequent implications upon the accuracy and the type of data needed are described in a qualitative manner. Whilst particular atomic and molecular processes are not discussed in detail, sufficient information is given of the physical environments of Tokamak devices for significant processes to be self evident. (author)

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

    Science.gov (United States)

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

    2013-10-01

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

  14. Survey of tritium wastes and effluents in near-term fusion-research facilities

    International Nuclear Information System (INIS)

    Bickford, W.E.; Dingee, D.A.; Willingham, C.E.

    1981-08-01

    The use of tritium control technology in near-term research facilities has been studied for both the magnetic and inertial confinement fusion programs. This study focused on routine generation of tritium wastes and effluents, with little referene to accidents or facility decommissioning. This report serves as an independent review of the effectiveness of planned control technology and radiological hazards associated with operation. The facilities examined for the magnetic fusion program included Fusion Materials Irradiation Testing Facility (FMIT), Tritium Systems Test Assembly (TSTA), and Tokamak Fusion Test Reactor (TFTR) in the magnetic fusion program, while NOVA and Antares facilities were examined for the inertial confinement program

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

    International Nuclear Information System (INIS)

    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

  16. A schedule for fusion research development and international collaboration

    International Nuclear Information System (INIS)

    Kakihana, H.

    1983-01-01

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

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

    International Nuclear Information System (INIS)

    Mann, L.; Glasser, A.; Sauthoff, N.

    1991-01-01

    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

  18. 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

  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

  20. The scientific benefits of inertially confined fusion research

    International Nuclear Information System (INIS)

    Key, M

    1999-01-01

    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

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

    International Nuclear Information System (INIS)

    1971-01-01

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

  2. Support and development for remote collaborations in fusion research

    International Nuclear Information System (INIS)

    Casper, T.A.; Jong, R.A.; Meyer, W.H.; Moller, J.M.

    2000-01-01

    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

  3. Support and development for remote collaboration in fusion research

    International Nuclear Information System (INIS)

    Casper, T A; Jong, R A; Meyer, W H; Moller, J M

    1999-01-01

    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

  4. Implications of NSTX lithium results for magnetic fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Ono, M., E-mail: mono@pppl.gov [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Bell, M.G.; Bell, R.E.; Kaita, R.; Kugel, H.W.; LeBlanc, B.P. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Canik, J.M.; Diem, S. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Gerhardt, S.P.; Hosea, J.; Kaye, S.; Mansfield, D. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Maingi, R. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Menard, J.; Paul, S.F. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Raman, R. [University of Washington at Seattle, Seattle, WA (United States); Sabbagh, S.A. [Columbia University, New York, NY (United States); Skinner, C.H. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Soukhanovskii, V. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Taylor, G. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States)

    2010-11-15

    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 {approx}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.

  5. Implications of NSTX Lithium Results for Magnetic Fusion Research

    International Nuclear Information System (INIS)

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

    2010-01-01

    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.

  6. Implications of NSTX lithium results for magnetic fusion research

    International Nuclear Information System (INIS)

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

    2010-01-01

    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.

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

    International Nuclear Information System (INIS)

    Dingee, D.A.

    1979-01-01

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

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

    International Nuclear Information System (INIS)

    1983-01-01

    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

  9. [Fusion research/tokamak]. Final report, 1 May 1988 - 30 April 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The objectives of the Fusion Research Center Program are: (1) to advance /the transport studies of tokamaks, including the development and maintenance of the Magnetic Fusion Energy Database, and (2) to provide theoretical interpretation, modeling and equilibrium and stability studies for the text-upgrade tokamak. Work is described on five basic categories: (1) magnetic fusion energy database; (2) computational support and numerical modeling; (3) support for TEXT-upgrade and diagnostics; (4) transport studies; and (5) Alfven waves

  10. Conceptual design of a mirror reactor for a fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Batzer, T.H.; Burleigh, R.C.; Carlson, G.A.; Dexter, W.L.; Hamilton, G.W.; Harvey, A.R.; Hickman, R.G.; Hoffman, M.A.; Hooper, E.B. Jr.; Moir, R.W.; Nelson, R.L.; Pittenger, L.C.; Smith, B.H.; Taylor, C.E.; Werner, R.W.; Wilcox, T.P.

    1975-01-01

    A conceptual design is presented for a small mirror fusion reactor for a Fusion Engineering Research Facility (FERF). The reactor produces 3.4 MW of fusion power and a useful neutron flux of about 10 14 n.cm -2 .s -1 . Superconducting ''yin-yang'' coils are used, and the plasma is sustained by injection of energetic neutral D 0 and T 0 . Conceptual layouts are given for the reactor, its major components, and supporting facilities. (author)

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

    International Nuclear Information System (INIS)

    Kubo, Hirotaka; Hoshino, Katsumichi; Isei, Nobuaki; Nakamura, Hiroo; Sato, Satoshi; Shimada, Katsuhiro; Sugie, Tatsuo

    2009-01-01

    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 (β N ) with good confinement (β N =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

  12. [A preliminary research on multi-source medical image fusion].

    Science.gov (United States)

    Kang, Yuanyuan; Li, Bin; Tian, Lianfang; Mao, Zongyuan

    2009-04-01

    Multi-modal medical image fusion has important value in clinical diagnosis and treatment. In this paper, the multi-resolution analysis of Daubechies 9/7 Biorthogonal Wavelet Transform is introduced for anatomical and functional image fusion, then a new fusion algorithm with the combination of local standard deviation and energy as texture measurement is presented. At last, a set of quantitative evaluation criteria is given. Experiments show that both anatomical and metabolism information can be obtained effectively, and both the edge and texture features can be reserved successfully. The presented algorithm is more effective than the traditional algorithms.

  13. 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 H-mode 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

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-02-15

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

  16. Assessment of contemporary mathematical methods for magnetic fusion research

    International Nuclear Information System (INIS)

    Treve, Y.M.

    1978-03-01

    The mathematical techniques reviewed have been selected on the basis of their relevance to at least four outstanding theoretical problems of magnetic fusion research, namely: (a) ion heating; (b) particle-wave interactions; (c) stability of magnetic surfaces in real tokamaks; and (d) strong plasma turbulence. These problems have a common feature: they all involve chaotic motions in spite of the perfectly deterministic nature of the mathematical models used for their description. In the first section devoted to Hamiltonian systems we briefly review the essentials of the Hamilton-Jacobi theory and discuss the Kolmogorov-Arnold-Moser theorem and its implications. In section 2 we review the difficulties of the problem of turbulence and present the Ruelle-Takens picture. An example of a dynamical system with a strange attractor is constructed and the Hopf bifurcation theory is discussed. Finally we review the properties of the Lorenz model for the convective instability of an atmospheric layer which is known to have a strange attractor for sufficiently high Rayleigh numbers

  17. 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.

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

    International Nuclear Information System (INIS)

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

    1995-05-01

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

  19. ITER: Fusion research at the dawn of a new era

    International Nuclear Information System (INIS)

    Aymar, R.

    2002-01-01

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

  20. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, T.; Nagayama, Y.; Nakanishi, H.; Ishiguro, S.; Takami, S.; Tsuda, K.; Okamura, S. [National Institute for Fusion Science, National Institutes of Natural Sciences, Toki (Japan)

    2009-07-01

    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)

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

    International Nuclear Information System (INIS)

    Conscience, J.-F.

    2003-01-01

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

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

    International Nuclear Information System (INIS)

    Zohm, Hartmut

    2009-01-01

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

  4. Materials research and development for fusion energy applications

    International Nuclear Information System (INIS)

    Zinkle, S.J.; Snead, L.L.

    1998-01-01

    Some of the critical issues associated with materials selection for proposed magnetic fusion reactors are reviewed, with a brief overview of refractory alloys (vanadium, tantalum, molybdenum, tungsten) and primary emphasis on ceramic materials. SiC/SiC composites are under consideration for the first wall and blanket structure, and dielectric insulators will be used for the heating, control and diagnostic measurement of the fusion plasma. Key issues for SiC/SiC composites include radiation-induced degradation in the strength and thermal conductivity. Recent work has focused on the development of radiation-resistant fibers and fiber/matrix interfaces (porous SiC, SiC multilayers) which would also produce improved SiC/SiC performance for applications such as heat engines and aerospace components. The key physical parameters for dielectrics include electrical conductivity, dielectric loss tangent and thermal conductivity. Ionizing radiation can increase the electrical conductivity of insulators by many orders of magnitude, and surface leakage currents can compromise the performance of some fusion energy components. Irradiation can cause a pronounced degradation in the loss tangent and thermal conductivity. Fundamental physical parameter measurements on ceramics which are of interest for both fusion and non-fusion applications are discussed

  5. Fiber optic transmission system delivered to Fusion Research Center of Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Hayashida, Mutsuo; Hiramoto, Kiyoshi; Yamazaki, Kunihiro

    1983-01-01

    In general there are many electromagnetically induced noises in the premises of factories, power plants and substations. Under such electrically bad environments, for the computer data transmission that needs high speed processing and high reliability, the optical fiber cable is superion to the coaxial cable or the flat-type cable in aspects of the inductionlessness and a wide bandwidth. Showa Electric Wire and Cable Co., Ltd. has delivered and installed a computer data transmission system consisting of optical modems and optical fiber cables for connecting every experiment building in the premises of Fusion Research Center of Japan Atomic Energy Research Institute. This paper describes the outline of this system. (author)

  6. Magnetic fusion energy and computers: the role of computing in magnetic fusion energy research and development

    International Nuclear Information System (INIS)

    1979-10-01

    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

  7. Research on fusion algorithm of polarization image in tetrolet domain

    Science.gov (United States)

    Zhang, Dexiang; Yuan, BaoHong; Zhang, Jingjing

    2015-12-01

    Tetrolets are Haar-type wavelets whose supports are tetrominoes which are shapes made by connecting four equal-sized squares. A fusion method for polarization images based on tetrolet transform is proposed. Firstly, the magnitude of polarization image and angle of polarization image can be decomposed into low-frequency coefficients and high-frequency coefficients with multi-scales and multi-directions using tetrolet transform. For the low-frequency coefficients, the average fusion method is used. According to edge distribution differences in high frequency sub-band images, for the directional high-frequency coefficients are used to select the better coefficients by region spectrum entropy algorithm for fusion. At last the fused image can be obtained by utilizing inverse transform for fused tetrolet coefficients. Experimental results show that the proposed method can detect image features more effectively and the fused image has better subjective visual effect

  8. Engineering Status of the Fusion Ignition Research Experiment (FIRE)

    International Nuclear Information System (INIS)

    Heitzenroeder, Philip J.; Meade, Dale; Thome, Richard J.

    2000-01-01

    FIRE is a compact, high field tokamak being studied as an option for the next step in the US magnetic fusion energy program. FIRE's programmatic mission is to attain, explore, understand, and optimize alpha-dominated plasmas to provide the knowledge necessary for the design of attractive magnetic fusion energy systems. This study began in 1999 with broad participation of the US fusion community, including several industrial participants. The design under development has a major radius of 2 m, a minor radius of 0.525 m, a field on axis of 10T and capability to operate at 12T with upgrades to power supplies. Toroidal and poloidal field magnets are inertially cooled with liquid nitrogen. An important goal for FIRE is a total project cost in the $1B range. This paper presents an overview of the engineering details which were developed during the FIRE preconceptual design study in FY99 and 00

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

    International Nuclear Information System (INIS)

    2001-01-01

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

  10. 1983 Annual technical report on inertial fusion research

    International Nuclear Information System (INIS)

    Solomon, D.E.; Monsler, M.J.; Terry, N.C.

    1984-03-01

    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

  11. Research and development plan of fusion technologies in JAERI toward DEMO reactors

    International Nuclear Information System (INIS)

    Nishitani, Takeo; Hayashi, Takumi; Abe, Tetsuya; Akiba, Masato; Isono, Takaaki; Inoue, Takashi; Enoeda, Mikio; Okuno, Kiyoshi; Koizumi, Norikiyo; Sakamoto, Keishi; Sato, Satoshi; Jitsukawa, Shiro; Sugimoto, Masayoshi; Suzuki, Satoshi; Seki, Shogo; Takatsu, Hideyuki; Tanzawa, Sadamitsu; Tsuchiya, Kunihiko; Nishi, Masataka; Hayashi, Kimio; Matsui, Hideki; Yamanishi, Toshihiko; Watanabe, Kazuhiro

    2005-03-01

    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)

  12. A survey on publications in fusion research and technology science and technology indicators in fusion R and T

    International Nuclear Information System (INIS)

    Hillebrand, C.D.

    1999-01-01

    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)

  13. A survey on publications in fusion research and technology science and technology indicators in fusion R and T

    International Nuclear Information System (INIS)

    Hillebrand, C.-D.

    2001-01-01

    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)

  14. Laser development for laser fusion applications research. Progress report, October 1977--March 1978

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  16. Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2016

    Energy Technology Data Exchange (ETDEWEB)

    Wiffen, Frederick 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)

    2016-12-01

    This document summarizes FY2016 activities supporting the Office of Science, Office of Fusion Energy Sciences Materials Research for MFE carried out by ORNL. The organization of the report is mainly by material type, with sections on specific technical activities.

  17. Tritium inventory in fusion reactors. Summary report of the final research coordination meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2007-11-01

    Detailed discussions were held during the final Research Coordination Meeting (RCM) at IAEA Headquarters on 25-27 September 2006, with the aim of reviewing the work accomplished by the Coordinated Research Project (CRP) on 'Tritium Inventory in Fusion Reactors'. Participants summarized the specific results obtained during the final phase of the CRP, and considered the impact of the data generated on the design of fusion devices. Conclusions were formulated and several specific recommendations for future fusion machines were agreed. The discussions, conclusions and recommendations of the RCM are briefly described in this report. (author)

  18. 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.

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

    International Nuclear Information System (INIS)

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

    1980-01-01

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

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

    International Nuclear Information System (INIS)

    2013-11-01

    Controlled nuclear fusion is widely considered to represent a nearly unlimited source of energy. Recent progress in the quest for fusion energy includes the design and current construction of the International Thermonuclear Experimental Reactor (ITER), for which a licence has recently been obtained as a first of its kind fusion nuclear installation. ITER is designed to demonstrate the scientific and technological feasibility of fusion energy production in excess of 500 MW for several consecutive minutes. ITER, however, will not be able to address all the nuclear fusion technology issues associated with the design, construction and operation of a commercial fusion power plant. The demonstration of an adequate tritium or fuel breeding ratio, as well as the development, characterization and testing of structural and functional materials in an integrated nuclear fusion environment, are examples of issues for which ITER is unable to deliver complete answers. To fill this knowledge gap, several facilities are being discussed, such as the International Fusion Materials Irradiation Facility and, eventually, a fusion demonstration power plant (DEMO). However, for these facilities, a vast body of preliminary research remains to be performed, for instance, concerning the preselection and testing of suitable materials able to withstand the high temperature and pressure, and intense radiation environment of a fusion reactor. Given their capacity for material testing in terms of available intense neutron fluxes, dedicated irradiation facilities and post-irradiation examination laboratories, high flux research reactors or material test reactors (MTRs) will play an indispensable role in the development of fusion technology. Moreover, research reactors have already achieved an esteemed legacy in the understanding of material properties and behaviour, and the knowledge gained from experiments in fission materials in certain cases can be applied to fusion systems, particularly those

  1. 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.

  2. LLNL (Lawrence Livermore National Laboratory) research on cold fusion

    Energy Technology Data Exchange (ETDEWEB)

    Thomassen, K I; Holzrichter, J F [eds.

    1989-09-14

    With the appearance of reports on Cold Fusion,'' scientists at the Lawrence Livermore National Laboratory (LLNL) began a series of increasingly sophisticated experiments and calculations to explain these phenomena. These experiments can be categorized as follows: (a) simple experiments to replicate the Utah results, (b) more sophisticated experiments to place lower bounds on the generation of heat and production of nuclear products, (c) a collaboration with Texas A M University to analyze electrodes and electrolytes for fusion by-products in a cell producing 10% excess heat (we found no by-products), and (d) attempts to replicate the Frascati experiment that first found neutron bursts when high-pressure deuterium gas in a cylinder with Ti chips was temperature-cycled. We failed in categories (a) and (b) to replicate either the Pons/Fleischmann or the Jones phenomena. We have seen phenomena similar to the Frascati results, (d) but these low-level burst signals may not be coming from neutrons generated in the Ti chips. Summaries of our experiments are described in Section II, as is a theoretical effort based on cosmic ray muons to describe low-level neutron production. Details of the experimental groups' work are contained in the six appendices. At LLNL, independent teams were spontaneously formed in response to the early announcements on cold fusion. This report's format follows this organization.

  3. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    International Nuclear Information System (INIS)

    2014-02-01

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

  4. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-02-15

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

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

    International Nuclear Information System (INIS)

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

    1975-01-01

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

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

    International Nuclear Information System (INIS)

    1987-12-01

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

  7. The recent progress of laser fusion research and future scope

    International Nuclear Information System (INIS)

    Yamanaka, C.

    1986-01-01

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

  8. Progress in inertial fusion research at Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    Perkins, R.B.

    1981-01-01

    The Los Alamos Scientific Laboratory Inertial Confinement Fusion Program is reviewed. Experiments using the Helios CO 2 laser system delivering up to 6kJ on target are described. Because breakeven energy estimates for laser drivers of 1 μm and above have risen and there is a need for CO 2 experiments in the tens-of-kJ regime as soon as practical, a first phase of Antares construction is now directed toward completion of two of the six original modules in 1983. These modules are designed to deliver 40kJ of CO 2 laser light on target. (author)

  9. Laser-fusion research progress report, January--June 1976

    International Nuclear Information System (INIS)

    1976-08-01

    Three prototypical laser systems; iodine, and HF, are being developed. The iodine laser program is designed to delineate possible problem areas in the development of higher-power iodine lasers and to improve its efficiency to where net energy gain is possible using complex targets or hybrid, fusion-fission reactors. To provide data for the oxygen laser, studies are under way on excited-state production efficiencies, electron-beam device development, and low-pressure gain phenomena. In the HF-laser program, technology is being developed applicable to high-power, high-gain laser systems

  10. Fusion research at the Royal Institute of Technology in Stockholm 1978

    International Nuclear Information System (INIS)

    Lehnert, B.

    1978-01-01

    Summaries are given on the research activities in plasma physics and controlled fusion during 1977, and on the plans for research in 1978. The research programme includes investigations on plasma-neutral gas interaction and stability, magnetic confinement being mainly produced by poloidal fields, plasma heating, and reactor technology. (author)

  11. A Multi-Disciplinary University Research Initiative in Hard and Soft Information Fusion: Overview, Research Strategies and Initial Results

    Science.gov (United States)

    2010-07-01

    Multisource Information Fusion ( CMIF ) along with a team including the Pennsylvania State University (PSU), Iona College (Iona), and Tennessee State...License. 14. ABSTRACT The University at Buffalo (UB) Center for Multisource Information Fusion ( CMIF ) along with a team including the Pennsylvania...of CMIF current research on methods for Test and Evaluation ([7], [8]) involving for example large- factor-space experimental design techniques ([9

  12. The European fusion research and development programme and the ITER Project

    International Nuclear Information System (INIS)

    Green, B.J.

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    Cook, D.L.; Allshouse, G.O.; Bailey, J.

    1986-01-01

    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)

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

    International Nuclear Information System (INIS)

    Seidl, P.; Bangerter, R.; Celata, C.M.

    1996-08-01

    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

  15. Report of the summative evaluation by the advisory committee on fusion research and development

    International Nuclear Information System (INIS)

    2005-03-01

    The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an Advisory Committee on Fusion Research and Development in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Fusion Research and Development evaluated the adequacy of the plans of fusion research and development to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of eight specialists from outside the JAERI conducted its activities from June 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Advisory Committee meeting which was held on July 23, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Fusion Research and Development. (author)

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

    International Nuclear Information System (INIS)

    2004-01-01

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

  17. Report on the research and development work of 1984 in the project atomic fusion

    International Nuclear Information System (INIS)

    Finken, D.

    1985-02-01

    The work done by the Nuclear Research Centre in Karlsruhe on fusion under magnetic influence is compiled in the project atomic fusion and put in the programme for European Fusion Technology. The work is supported by an association contract between KfK and Euratom via the European Commission. Some of the work exceeds the volume defined in the E.E.C's technology programme. Using these papers, mostly studies, connections are established between the various fields of work and new tasks prepared. This is taking place in the light of the expected extension of the technology programme in the coming year and the plans for NET. The reports compiled here are the 1984 papers from the KfK institute. The appendix contains a compilation of the tasks undertaken by KfK from the EEC's fusion technology programme. (orig./GG) [de

  18. Teaching and research in fusion plasmas and technology at the University of Illinois

    International Nuclear Information System (INIS)

    Miley, G.H.; Southworth, F.H.

    1975-01-01

    Teaching in fusion at the University of Illinois is an integrated part of the nuclear engineering curriculum. Through the use of two key courses, ''Introduction to Fusion'' and ''Fusion Systems,'' basic preparation for those wishing to specialize in fusion is provided. These courses are primarily directed to plasma aspects of fusion, but materials and other engineering aspects have been integrated into the curriculum through a broadened coverage in such existing courses as nuclear materials, shielding, and reactor physics. Research is primarily focused at the PhD level, although some MS studies are in progress. While current theses involve a wide variety of topics, one major area being pursued is the study of advanced fuel (non-deuterium-tritium) reactors based on two-component fusion and other concepts. This effort consists of a series of loosely knit subtasks related to such problems as cyclotron emission and direct energy conversion. Also, various research involving charge-exchange losses during neutral-beam injection, vacuum-wall sputtering, and related topics has developed as a direct outgrowth of the PROMETHEUS project, which involved the conceptual design of a power-consuming mirror-type reactor for materials and engineering tests

  19. Research programme on controlled thermonuclear fusion. Synthesis report 2011; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2011

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2012-07-01

    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), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. 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. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma

  20. Fusion Reactor Safety Research program. Annual report, FY-80

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1981-06-01

    The report is in three sections. Outside contracts includes a report of newly-started study at the General Atomic Company to consider safety implications of low-activation materials, portions of two papers from ongoing work at PNL and ANL, reports of the lithium spill work at HEDL, the LITFIRE code development at MIT, and risk assessment at MIT, all of which are an expansion of FY-79 outside contracts. EG and G Activities includes adaptations of four papers of ongoing work in transient code development, tritium system risk assessment, heat transfer and fluid flow analysis, and fusion safety data base. Program Plan Development includes the Executive Summary of the Plan, which was completed in FY-80, and is accompanied by a list of publications and a brief outline of proposed FY-81 activities to be based on the Program Plan

  1. ITER: Fusion research at the dawn of a new era

    International Nuclear Information System (INIS)

    Aymar, R.; Chuyanov, V.; Shimomura, Y.; Huguet, M.

    2003-01-01

    Given the expected success of on-going negotiations on the Joint Implementing Agreement for ITER construction and operation, a new era is opening for experimentation with reactor-relevant physics integrated with key reactor technologies in a licensed nuclear environment. The ITER design, cost estimate and safety analysis are supported by a large body of validating physics and technology R and D. The main features of the design, and analysis of its performance, give confidence that it will fulfil its technical objectives and demonstrate the environmental attractiveness of fusion. This paper gives illustrative confirmation of these expectations and an update on the technical preparations for construction, as well as the status of negotiations. (author)

  2. Sandia's recent results in particle beam fusion research

    International Nuclear Information System (INIS)

    Yonas, G.

    Sandia's latest achievements in the particle beam fusion program are enumerated and pulse power accelerators offering a route to an experimental reactor ignition system are discussed. Four interdependent elements of the program are investigated: 1) power concentration and dielectric breakdown, 2) beam focusing and transport, 3) beam target interaction, and 4) implosion hydrodynamics. Results of the spherical target irradiation experiment on the 1 TW Proto I accelerator and the successful neutron production experiment using the 0.25 TW electron beam from the Rehyd generator are reported. Beam propagation in plasma discharge channels and magnetically insulated vacuum transmission lines have been tested as alternative ways of the power transport. The first-time operation of the Proto II accelerator at 6 TW level is the first step in scaling of intense particle accelerators to higher power levels. (J.U.)

  3. First IAEA research co-ordination meeting on 'Tritium inventory in fusion reactors'. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2003-02-01

    The proceedings and conclusions of the first Research Co-ordination Meeting on 'Tritium Inventory in Fusion Reactors', held on November 4-6, 2002 at the IAEA Headquarters in Vienna are briefly described. This report includes a summary of the presentations made by the meeting participants and the specific goals set by the participants of the Co-ordinated Research Project (CRP). (author)

  4. Forty years of inertial confinement fusion research in the Shanghai Institute of Optics and Fine Mechanics

    International Nuclear Information System (INIS)

    Chen Chongbin; Wang Letian

    2010-01-01

    On the basis of China's own technology and industry, the 'Shenguang' inertial confinement fusion (ICF) research devices were built, and a series of world-class results achieved. In this paper, the history of ICF research in the Shanghai Institute of Optics and Fine Mechanics is reviewed. (authors)

  5. Methods of economic analysis applied to fusion research. Fourth annual report

    International Nuclear Information System (INIS)

    Hazelrigg, G.A. Jr.

    1980-01-01

    The current study reported here has involved three separate tasks. The first task deals with the development of expected utility analysis techniques for economic evaluation of fusion research. A decision analytic model is developed for the incorporation of market uncertainties, as well as technological uncertainties in an economic evaluation of long-range energy research. The model is applied to the case of fusion research. The second task deals with the potential effects of long-range energy RD and D on fossil fuel prices. ECON's previous fossil fuel price model is extended to incorporate a dynamic demand function. The dynamic demand function supports price fluctuations such as those observed in the marketplace. The third task examines alternative uses of fusion technologies, specifically superconducting technologies and first wall materials to determine the potential for alternative, nonfusion use of these technologies. In both cases, numerous alternative uses are found

  6. IAEA workshop on 'Atomic and molecular data for fusion energy research'. Summary report

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2004-05-01

    On September 8-12 a workshop on Atomic and Molecular (A+M) Data for Fusion Energy Research was hosted by the International Centre for Theoretical Physics in Trieste Italy. The workshop was attended by twelve students representing eleven Member States. A total of five lecturers, including four external to the Agency, made presentations to the workshop. All lecturers provided advance copies of the lecture materials and all provided written assignments for the students, to provide practical examples of applications of data issues to actual problems related to fusion energy research. All materials were collected on CDs, which were distributed to the students by the conclusion of the workshop. During the course of the workshop the students were given the opportunity to describe their backgrounds and research interests. The workshop did arouse interest in A+M processes related to fusion. The workshop was viewed as successful by the students. (author)

  7. Summary report of IAEA workshop on atomic and molecular data for fusion energy research

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2007-02-01

    A workshop on Atomic and Molecular (A+M) Data for Fusion Energy Research was held at the International Centre for Theoretical Physics (ICTP) in Trieste, Italy, from 28 August until 8 September 2006. The workshop was attended by fourteen students and three ICTP associates representing eleven Member States. A total of eight lecturers, including six external to the Agency, made presentations to the workshop. All lecturers provided advance copies of the lecture materials, and provided written assignments for the students to provide practical examples of applications of data issues to actual problems related to fusion energy research. All materials were collected on CDs, which were distributed to the students at the conclusion of the workshop. During the course of the workshop, the students were given the opportunity to describe their background and research interests. The workshop did arouse interest in A+M processes related to fusion, and was viewed as successful by both the students and lecturers. (author)

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

    International Nuclear Information System (INIS)

    Post, R.F.

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    Bullis, R.; Finkelman, M.; Leng, J.; Luzzi, T.; Ojalvo, I.; Powell, E.; Sedgley, D.

    1980-08-01

    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

  10. Summary report of second IAEA research coordination meeting on tritium inventory in fusion reactors

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2006-03-01

    Detailed discussions were held during an RCM at IAEA Headquarters on 18-19 October 2004 to review the progress made in the CRP on 'Tritium Inventory in Fusion Reactors'. Participants summarized the specific results obtained during the initial phase of the Coordinated Research Project (CRP), and considered the impact of the data generated on the design of fusion devices. Areas with further research needs were identified, and a set of outstanding objectives was formulated for the continuation of the CRP. The discussions, conclusions and recommendations of the RCM are briefly described in this report. (author)

  11. Italy, EURATOM and Early Research on Controlled Thermonuclear Fusion (1957-1962)

    International Nuclear Information System (INIS)

    Curli, Barbara

    2017-01-01

    This chapter traces the early origins of European collaboration in controlled thermonuclear fusion research, within the larger picture of Cold War nuclear policy in the late 1950s-early 1960s, and as a consequence of the signing of the EURATOM treaty in 1957. It then presents some preliminary findings on the Association contract which was signed in 1960 between EURATOM and Italy, in order to carry out research in controlled thermonuclear fusion at the then newly created 'Laboratori nazionali di Frascati', near Rome, within the framework of the Comitato Nazionale Energia Nucleare (CNEN), the Italian civilian nuclear energy agency.

  12. Controlled Nuclear Fusion Research, September 1965: Review Of Experimental Results

    Energy Technology Data Exchange (ETDEWEB)

    Spitzer, Lyman Jr. [Princeton University, Princeton, NJ (United States)

    1966-04-15

    To my way of thinking the most significant milestone of the present meeting is the substantial body of evidence that has been presented on the hydromagnetic stabilization of open-ended systems. The success of minimum magnetic-field ('minimum-B') configurations in stabilizing a plasma marks one more area where theory and experiment in the field of plasma physics have been brought together with gratifying results. Let me go back a little into history and discuss the gradual growth of our information on hydromagnetic instabilities generally. Many of you will remember that hydromagnetic theory was applied to the self-pinched discharge in the early years of the controUed fusion programme. The predictions of this theory were very shortly fulfilled by the observations; the effects were so unmistakable that it was not difficult to compare the theory with the observations. On the streak pictures of the linear or toroidal discharges that were obtained in those early years one saw clearly the diffuse plasma column, which first contracted to a narrow filament and then started to distort and kink until finally it hit the wall. Under some conditions the plasma was observed to break up into a series of blobs like a string of sausages. Since the behaviour was exactly what the theory had predicted, it took no very great experimental wisdom to conclude that observations had confirmed theory.

  13. Fusion power

    International Nuclear Information System (INIS)

    Hancox, R.

    1981-01-01

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

  14. Present status of design, research and development of nuclear fusion reactors and problems

    International Nuclear Information System (INIS)

    1983-04-01

    Seven years have elapsed since the publication of ''Progress of nuclear fusion research and perspective toward the development of power reactors'' by the Atomic Energy Society of Japan in August, 1976. During this period, the research and development of nuclear fusion have changed from plasma physics to reactor technology, being conscious of the realization of fusion reactors. There are the R project in the Institute of Plasma Physics, Nagoya University, and the design and construction of JT-60 in Japan Atomic Energy Research Institute, to put it concretely. Now the research and development taking the economical efficiency into account are adopted. However, the type of fusion reactors is not reduced to tokamak type, accordingly the research and development to meet the diverse possibilities are forwarded. The progress of tokamak reactor research, core plasma design, nuclear design and shielding design, thermal structure design, the design of superconducting magnets, disassembling and repair, safety, economical efficiency, the conceptual design of other types than tokamak and others are reported. (Kako, I.)

  15. Fusion: introduction

    International Nuclear Information System (INIS)

    Decreton, M.

    2006-01-01

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

  16. Thermonuclear fusion: from fundamental research to energy production? Science and technology report No. 26

    International Nuclear Information System (INIS)

    Laval, Guy; Blanzat, Bernard; Aspect, Alain; Aymar, Robert; Bielak, Bogdan; Decroisette, Michel; Martin, Georges; Andre, Michel; Schirmann, Daniel; Garbet, Xavier; Jacquinot, Jean; Laviron, Clement; Migus, Arnold; Moreau, Rene; Pironneau, Olivier; Quere, Yves; Vallee, Alain; Dercourt, Jean; Bayer, Charles; Juraszek, Denis; Deutsch, Claude; Le Garrec, Bruno; Hennequin, Pascale; Peysson, Yves; Rax, Jean-Marcel; Pesme, Denis; Bauche, Jacques; Monier-Garbet, Pascale; Stamm, Roland; Zerah, Gilles; Ghendrih, Philippe; Layet, Roland; Grosman, Andre; Alamo, Ana; Giancarli, Luciano; Poitevin, Yves; Rigal, Emmanuel; Chieze, Jean-Pierre

    2007-01-01

    This work has been commissioned by the French ministry of Education, Sciences and Research, its aim is to provide a reliable account of the state of development of thermonuclear fusion. This report makes a point on the scientific knowledge accumulated on the topic and highlights the research programs that are necessary to overcome the technological difficulties and draws the necessary steps before an industrial application to electricity production. This report is divided into 10 chapters: 1) tokamak technology and ITER, 2) inertial fusion, 3) magnetized hot plasmas, 4) laser-plasma interaction and peta-watt lasers, 5) atomic physics and fusion, 6) computer simulation, 7) plasma-wall interaction, 8) materials for fusion reactors, 9) safety analysis, and 10) inertial fusion and astrophysics. This report has been written by a large panel of experts gathered by the French Academy of Sciences. The comments on the issue by the 3 French organizations: Cea, Cnrs and SFP (French Society of Physics) follow the last chapter

  17. Research programme on controlled thermonuclear fusion - Synthesis report 2010; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2010

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2011-07-01

    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

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

    International Nuclear Information System (INIS)

    1980-01-01

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

    Highlights: • The safety characteristics and at risk inventories in an IFE facility are discussed. • The primary nuclear hazard is the potential exposure of workers and/or the public to tritium and/or neutronically activated products. • Recent technology developments in tritium processing are key for minimization of inventories. • Initial safety studies indicate that hazards associated to the use of liquid lithium can be appropriately managed. • Simulation of worst-case scenarios indicate that the accident consequences are limited and below the limit for public evacuation. - Abstract: Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-11-01

    Highlights: • The safety characteristics and at risk inventories in an IFE facility are discussed. • The primary nuclear hazard is the potential exposure of workers and/or the public to tritium and/or neutronically activated products. • Recent technology developments in tritium processing are key for minimization of inventories. • Initial safety studies indicate that hazards associated to the use of liquid lithium can be appropriately managed. • Simulation of worst-case scenarios indicate that the accident consequences are limited and below the limit for public evacuation. - Abstract: Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and

  1. Polarization plasma spectroscopy (PPS) viewed from plasma physics and fusion research

    International Nuclear Information System (INIS)

    Ida, Katsumi

    1998-01-01

    Recently the measurements of poloidal magnetic field become important in plasma physics and nuclear fusion research, since an improved confinement mode associating with a negative magnetic shear has been found. The polarization plasma spectroscopy is recognized to be a useful tool to measure poloidal magnetic field and pitch angle of magnetic field. (author)

  2. IAEA technical committee meeting on research using small fusion devices (abstracts)

    International Nuclear Information System (INIS)

    1999-12-01

    The thirteenth IAEA technical committee meeting on research using small fusion devices are held in Chengdu, P. R. China on 18-20 Oct. , 1999. 41 articles are received and the content includes toroidal systems, helical systems, plasma focus, diagnostic systems, theory and modeling, improving confinement, numerical simulation, innovative concepts and others

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  4. Fusion energy research, the tokamak of CRPP-EPFL, electrotechnical equipment

    International Nuclear Information System (INIS)

    1993-01-01

    The topics of this information meeting were: fusion energy research at CRPP, the TCV tokamak, an alternating current generator which does not stress the grid, AC/DC multi-megawatt converters, stabilisation of the plasma, a fast and modular power AC/DC converter. figs., tabs., refs

  5. High-power pulsed light ion beams for applications in fusion- and matter research

    International Nuclear Information System (INIS)

    Bluhm, H.; Karow, H.U.; Rusch, D.; Zieher, K.W.

    1982-01-01

    The foundations of ultrahigh-power pulse techniques are described together with the two pulse generators KALIF (Karlsruhe Light lion Facility) and Pollux of the INR. The physical principles and diagnostics of ion beam production are discussed as well as possible applications in the field of fusion research. (orig./HT) [de

  6. Preparation of processed nuclear data libraries for thermal, fast and fusion research and power reactor applications

    International Nuclear Information System (INIS)

    Ganesan, S.

    1994-03-01

    A Consultants Meeting on ''Preparation of Processed Nuclear Data Libraries for Thermal, Fast and Fusion Research and Power Reactor Applications'' was convened by the International Atomic Energy Agency and held during December 13-16, 1993 December 8-10, 1993 at the IAEA Headquarters, Vienna. The detailed agenda, the complete list of participants and the recommendations are presented in this report. (author)

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

    International Nuclear Information System (INIS)

    Ueda, M.

    1992-05-01

    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.)

  8. The tritium monitoring requirements of fusion and the status of research

    International Nuclear Information System (INIS)

    Nickerson, S.B.; Gerdingh, R.F.; Penfold, K.

    1982-10-01

    This report is a summary of an investigation into the tritium monitoring requirements of tritium laboratories, D-T burning ignition experiments, and fusion reactors. There is also a summary of the status of research into tritium monitoring and a survey of commercially available tritium monitors

  9. Pacific Northwest Laboratory report on fusion energy research, April 1977 - June 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-07-01

    The development of economic data for fusion power plants continued in a study estimating the potential impact of a shortage of materials important in fusion plant construction. In studies developing heat transfer and fluid flow design tools for fusion reactor blankets, preconceptual design studies were initiated to identify the potential design limits of water cooling in the first wall of Tokamak Next Step (TNS) concepts. In surface effects research clean gold samples were irradiated in the University of California (D,Be) neutron source for a neutron sputtering experiment. Light ion and neutron irradiation experiments have continued in studies of the effects of radiation on mechanical properties. The hardening response of 14 MeV neutron-irradiated nickel changed at high particle fluences (10/sup 16/ to 10/sup 17/ particles/cm/sup 2/) while the hardening response of 16 MeV proton-irradiated nickel did not, which may have been due to a difference in irradiation hardening mechanisms. The flux dependence of the damage microstructure and irradiation hardening of materials needs further study to clarify uncertainty about light ion and fusion neutron damage processes. Neutron irradiations of Ni, 316SS, and Nb wires and foils were completed. Work has continued in studies developing acoustic emission (AE) techniques for determining the prebreakdown behavior and failure mechanisms in electric insulators with potential applications in fusion reactors. Scoping experiments with the high-vacuum dielectric breakdown apparatus were conducted.

  10. Overview of Heavy Ion Fusion Accelerator Research in the U. S.

    Science.gov (United States)

    Friedman, Alex

    2002-12-01

    This article provides an overview of current U.S. research on accelerators for Heavy Ion Fusion, that is, inertial fusion driven by intense beams of heavy ions with the goal of energy production. The concept, beam requirements, approach, and major issues are introduced. An overview of a number of new experiments is presented. These include: the High Current Experiment now underway at Lawrence Berkeley National Laboratory; studies of advanced injectors (and in particular an approach based on the merging of multiple beamlets), being investigated experimentally at Lawrence Livermore National Laboratory); the Neutralized (chamber) Transport Experiment being assembled at Lawrence Berkeley National Laboratory; and smaller experiments at the University of Maryland and at Princeton Plasma Physics Laboratory. The comprehensive program of beam simulations and theory is outlined. Finally, prospects and plans for further development of this promising approach to fusion energy are discussed.

  11. The European fusion program and the role of the research reactors

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  12. Overview of heavy ion fusion accelerator research in the U.S

    International Nuclear Information System (INIS)

    Friedman, Alex

    2002-01-01

    This article provides an overview of current U.S. research on accelerators for Heavy Ion Fusion, that is, inertial fusion driven by intense beams of heavy ions with the goal of energy production. The concept, beam requirements, approach, and major issues are introduced. An overview of a number of new experiments is presented. These include: the High Current Experiment now underway at Lawrence Berkeley National Laboratory; studies of advanced injectors (and in particular an approach based on the merging of multiple beamlets), being investigated experimentally at Lawrence Livermore National Laboratory); the Neutralized (chamber) Transport Experiment being assembled at Lawrence Berkeley National Laboratory; and smaller experiments at the University of Maryland and at Princeton Plasma Physics Laboratory. The comprehensive program of beam simulations and theory is outlined. Finally, prospects and plans for further development of this promising approach to fusion energy are discussed

  13. Overview of Heavy Ion Fusion Accelerator Research in the U.S

    International Nuclear Information System (INIS)

    Friedman, A

    2002-01-01

    This article provides an overview of current U.S. research on accelerators for Heavy Ion Fusion, that is, inertial fusion driven by intense beams of heavy ions with the goal of energy production. The concept, beam requirements, approach, and major issues are introduced. An overview of a number of new experiments is presented. These include: the High Current Experiment now underway at Lawrence Berkeley National Laboratory; studies of advanced injectors (and in particular an approach based on the merging of multiple beamlets), being investigated experimentally at Lawrence Livermore National Laboratory; the Neutralized (chamber) Transport Experiment being assembled at Lawrence Berkeley National Laboratory; and smaller experiments at the University of Maryland and at Princeton Plasma Physics Laboratory. The comprehensive program of beam simulations and theory is outlined. Finally, prospects and plans for further development of this promising approach to fusion energy are discussed

  14. Discourse, Power, and Knowledge in the Management of "Big Science": The Production of Consensus in a Nuclear Fusion Research Laboratory.

    Science.gov (United States)

    Kinsella, William J.

    1999-01-01

    Extends a Foucauldian view of power/knowledge to the archetypical knowledge-intensive organization, the scientific research laboratory. Describes the discursive production of power/knowledge at the "big science" laboratory conducting nuclear fusion research and illuminates a critical incident in which the fusion research…

  15. Data management, code deployment, and scientific visualization to enhance scientific discovery in fusion research through advanced computing

    International Nuclear Information System (INIS)

    Schissel, D.P.; Finkelstein, A.; Foster, I.T.; Fredian, T.W.; Greenwald, M.J.; Hansen, C.D.; Johnson, C.R.; Keahey, K.; Klasky, S.A.; Li, K.; McCune, D.C.; Peng, Q.; Stevens, R.; Thompson, M.R.

    2002-01-01

    The long-term vision of the Fusion Collaboratory described in this paper is to transform fusion research and accelerate scientific understanding and innovation so as to revolutionize the design of a fusion energy source. The Collaboratory will create and deploy collaborative software tools that will enable more efficient utilization of existing experimental facilities and more effective integration of experiment, theory, and modeling. The computer science research necessary to create the Collaboratory is centered on three activities: security, remote and distributed computing, and scientific visualization. It is anticipated that the presently envisioned Fusion Collaboratory software tools will require 3 years to complete

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

    International Nuclear Information System (INIS)

    2013-04-01

    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.

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

    Czech Academy of Sciences Publication Activity Database

    Gryaznevich, M.; Van Oost, G.; Stöckel, Jan; Kamendje, R.; Kuteev, B.N.; Melnikov, A.; Popov, T.; Svoboda, V.

    2015-01-01

    Roč. 55, č. 10 (2015), s. 104019-104019 ISSN 0029-5515. [Fusion Energy Conference 2014 (FEC) /25./. St Petersburg, 13.10.2014-18.10.2014] Institutional support: RVO:61389021 Keywords : IAEA CRP * IAEA JE * small tokamaks * fusion neutron source Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 4.040, year: 2015 http://iopscience.iop.org/0029-5515/55/10/104019

  18. An exploration for a feasible fusion energy research strategy in Korea

    International Nuclear Information System (INIS)

    Kim, Sung Kyu; Park, Jong Kyun; Yang, Maeng Ho

    2005-01-01

    Recently, the fierce competition between European Union (EU) and Japan to host the International Thermo-nuclear Experimental Reactor (ITER) has aroused in Korea renewed interests in fusion research and its pros-pect for commercial fusion power generation. Korea has committed itself in 2003 to the construction and operation of ITER which spans three decades. This 30-years-long commitment to ITER surely is longer than any other scientific and/or technological venture that has ever been taken up after its birth in 1948. ITER poses both as a great opportunity for Korea, allegedly but not convincingly enough, and as a potential 'black hole' sucking in all resources for future energy researches, to the domestic technical communities and industries. However, ITER and fusion research is not just a technico-industrial issue but may as well be a politico-security issue, like many other apparent technology issues such as recent participation in the Galileo project. In this article, the authors will explore this situation with an emphasis on domestic and foreign constraints and propose a realistic and verifiable strategy to address these issues and to develop fusion energy in Korea

  19. Energetic Particle Physics In Fusion Research In Preparation For Burning Plasma Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Gorelenkov, Nikolai N [PPPL

    2013-06-01

    The area of energetic particle (EP) physics of fusion research has been actively and extensively researched in recent decades. The progress achieved in advancing and understanding EP physics has been substantial since the last comprehensive review on this topic by W.W. Heidbrink and G.J. Sadler [1]. That review coincided with the start of deuterium-tritium (DT) experiments on Tokamak Fusion Test reactor (TFTR) and full scale fusion alphas physics studies. Fusion research in recent years has been influenced by EP physics in many ways including the limitations imposed by the "sea" of Alfven eigenmodes (AE) in particular by the toroidicityinduced AEs (TAE) modes and reversed shear Alfven (RSAE). In present paper we attempt a broad review of EP physics progress in tokamaks and spherical tori since the first DT experiments on TFTR and JET (Joint European Torus) including helical/stellarator devices. Introductory discussions on basic ingredients of EP physics, i.e. particle orbits in STs, fundamental diagnostic techniques of EPs and instabilities, wave particle resonances and others are given to help understanding the advanced topics of EP physics. At the end we cover important and interesting physics issues toward the burning plasma experiments such as ITER (International Thermonuclear Experimental Reactor).

  20. Magnetic mirror fusion research at the Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    Post, R.F.

    1979-01-01

    An overall view is given of progress and plans for pressing forward with mirror research at Livermore. No detail is given on any one subject, and many interesting investigations being carried out at University laboratories in the U.S. that augment and support efforts at Livermore are omitted

  1. Development of Laser Based Plasma Diagnostics for Fusion Research on NSTX-U

    Science.gov (United States)

    Barchfeld, Robert Adam

    Worldwide demand for power, and in particular electricity, is growing. Increasing population, expanding dependence on electrical devices, as well as the development of emerging nations, has created significant challenges for the power production. Compounding the issue are concerns over pollution, natural resource supplies, and political obstacles in troubled parts of the world. Many believe that investment in renewable energy will solve the expected energy crisis; however, renewable energy has many shortfalls. Consequently, additional sources of energy should be explored to provide the best options for the future. Electricity from fusion power offers many advantages over competing technologies. It can potentially produce large amounts of clean energy, without the serious concerns of fission power plant safety and nuclear waste. Fuel supplies for fusion are plentiful. Fusion power plants can be operated as needed, without dependence on location, or local conditions. However, there are significant challenges before fusion can be realized. Many factors currently limit the effectiveness of fusion power, which prevents a commercial power plant from being feasible. Scientists in many countries have built, and operate, experimental fusion plants to study the fusion process. The leading examples are magnetic confinement reactors known as tokamaks. At present, reactor gain is near unity, where the fusion power output is nearly the same as the power required to operate the reactor. A tenfold increase in gain is what reactors such as ITER hope to achieve, where 50 MW will be used for plasma heating, magnetic fields, and so forth, with a power output of 500 MW. Before this can happen, further research is required. Loss of particle and energy confinement is a principal cause of low performance; therefore, increasing confinement time is key. There are many causes of thermal and particle transport that are being researched, and the prime tools for conducting this research are

  2. ITER and research works on magnetic confinement fusion

    International Nuclear Information System (INIS)

    Jacquinot, J.

    2013-01-01

    This article presents the main features of the ITER tokamak and its implications in terms of research concerning plasma instabilities, confinement and materials. It also shows how the financial and technological responsibilities have been shared between the 7 partners (European Union, China, South-Korea, Russia, Japan, India and United-States) and also gives a progress update of the fabrication of the components at the date of September 2012

  3. Program for development of toroidal superconducting magnets for fusion research

    International Nuclear Information System (INIS)

    Long, H.M.; Lubell, M.S.

    1976-04-01

    Research progress on the following subprograms is described/: (1) system design, (2) coil design, (3) conductor selection and test, (4) radiation effects on superconducting coils, (5) coil protection, eddy current shielding, and power supply, (6) structural analysis and materials investigation, (7) cryogenics and refrigeration, (8) subsize coil fabrication, (9) large coil project, (10) coil testing and evaluation, (11) administrative plan, and (12) quality assurance and reliability

  4. Fusion research at the Royal Institute of Technology in Stockholm 1977

    International Nuclear Information System (INIS)

    Lehnert, B.

    1976-12-01

    Reviews are given on the research activities in plasma physics and controlled fusion during 1976 as well as on the plans for research in 1977, including short descriptions and motivations of the lines of approach being conducted by the laboratory. These lines include plasma-neutral gas interaction and stability, also with special approaches to plasma stabilization, magnetic confinement being mainly produced by poloidal fields, as well as heating and diagnostics of impermeable plasmas. (Auth.)

  5. Resolving key heavy-ion fusion target issues with relativistic heavy-ion research accelerators

    International Nuclear Information System (INIS)

    Arnold, R.C.

    1988-01-01

    Heavy-ion accelerators designed for relativistic nuclear research experiments can also be adapted for target research in heavy-ion driver inertial fusion. Needle-shaped plasmas can be created that are adequate for studying basic properties of matter at high energy density. Although the ion range is very long, the specific deposited power nevertheless increases with kinetic energy, as the focus spot can be made smaller and more ions can be accumulated in larger rings

  6. EDITORIAL: Safety aspects of fusion power plants

    Science.gov (United States)

    Kolbasov, B. N.

    2007-07-01

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

  7. Recent results and near-term expectations in Tokamak fusion research in the U.S., Europe, and Japan

    International Nuclear Information System (INIS)

    Meade, D.

    1993-01-01

    The development of fusion is often thought about in terms of three different activities: scientific feasibility, engineering feasibility, and economic feasibility. This paper discusses the scientific feasibility of fusion. Reactor temperatures, reactor densities and confinement, particle control, plasma power handling, and self-heating are some of the issues examined. Collaboration and results from research at the Tokamak Fusion Test Reactor (TFTR) at Princeton, the JT-60U in Japan, and JET, the Joint European Torus Tokamak in Oxford are presented

  8. Evaluation of the fusion technology and safety programme of the Joint Research Centre (1980-85)

    International Nuclear Information System (INIS)

    Haines, M.; Cabibbo, N.; Crocker, J.G.; Lecomte, M.; Merz, E.

    1986-01-01

    The Joint Research Centre, Ispra, has been involved in fusion research since 1973. In July 1985 the Commission of European Communities - DG XII, following a policy of systematically evaluating its RandD activities, appointed a panel of external experts to evaluate the fusion technology and safety programme carried out at the Joint Research Centre. This report describes the work of the panel in evaluating the research performed by the JRC within the framework of its 1984-87 programme. The achievements of the previous programme, 1980-83, were also taken into consideration. The different research areas covered in the programme, i.e.: reactor studies, breeding blanket technology, structural materials studies, risk assessment and tritium laboratory studies, are described and a draft proposal for the period 1987-90 presented. The evaluation panel has been asked to assess the following aspects: the scientific and technical achievements of the programme, the contribution of the programme to the development of other Community policies, the role played by the JRC in the European fusion research (including NET) and in international collaborations such as INTOR. From its assessment the evaluation panel has made a series of recommendations for the current programme and for future work

  9. Progress of JT-60SA Project: EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

    Energy Technology Data Exchange (ETDEWEB)

    Shirai, Hiroshi, E-mail: shirai.hiroshi@jaea.go.jp [JT-60SA Project Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan); Barabaschi, Pietro [JT-60SA EU-Home Team, Fusion for Energy, Boltsmannstr 2, Garching 85748 (Germany); Kamada, Yutaka [JT-60SA JA-Home Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan)

    2016-11-01

    Highlights: • JT-60SA Project is promoted under the BA Agreement and JA national programme. • JT-60SA is designed to operate in break-even equivalent condition for a long period. • JT-60SA Project supports and complements the ITER project, and promotes DEMO design. • Fabrication of JT-60SA components and assembly in Naka are steadily going on. • JT-60SA Research Plan has been developed jointly by EU and JA fusion communities. - Abstract: Aiming at supporting the early realization of fusion energy, the JT-60SA Project has shown steady progress for several years toward the first plasma in 2019 under the dual frameworks: the Satellite Tokamak Programme of the Broader Approach Agreement between EU and Japan, and the Japanese national programme. JT-60SA is a superconducting tokamak designed to operate in break-even equivalent conditions for a long pulse duration (typically 100 s) with a maximum plasma current of 5.5 MA. A variety of plasma control capabilities enable JT-60SA to contribute directly to the ITER project and also to DEMO by addressing key engineering and physics issues for advanced plasma operation. Design and fabrication of JT-60SA components, shared by the EU and Japan, started in 2007. Assembly in the torus hall started in January 2013, and welding work of the vacuum vessel sectors (seven 40° sectors and two 30° sectors) is currently ongoing on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so on were or are being delivered to the Naka site for installation, assembly and commissioning. This paper gives technical progress on fabrication, installation and assembly of tokamak components and ancillary systems, as well as progress of the JT-60SA Research Plan being developed jointly by European and Japanese fusion communities.

  10. The Status of Beryllium Research for Fusion in the United States

    International Nuclear Information System (INIS)

    Glen R. Longhurst

    2003-01-01

    Use of beryllium in fusion reactors has been considered for neutron multiplication in breeding blankets and as an oxygen getter for plasma-facing surfaces. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling and changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Thermonuclear Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied to better understand important processes and to assist with design. Presently, studies are underway at the University of California Los Angeles to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling

  11. The status of beryllium research for fusion in the United States

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Snead, L.L.; Abou-Sena, A.A.

    2004-01-01

    Use of beryllium in fusion reactor has been considered for neutron multiplication in breeding blankets an as an oxygen getter for plasma - facing surface. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling an changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL (Idaho National Engineering and Environmental Laboratory) and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied at the University of California Los Angels to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling. (author)

  12. The European Fusion Research and Development Programme and the ITER Project

    International Nuclear Information System (INIS)

    Green, B J

    2006-01-01

    The EURATOM fusion research and development programme is a well integrated and coordinated programme. It has the objective of ''developing the technology for a safe, sustainable, environmentally responsible and economically viable energy source.'' The programme is focussed on the magnetic confinement approach and supports 23 Associations which involve research entities (many with experimental and technology facilities) each having a bilateral contractual relationship with the European Commission. The paper will describe fusion reactions and present their potential advantages as an energy source. Further, it will describe the EURATOM programme and how it is organised and implemented. The success of the European programme and that of other national programmes, have provided the basis for the international ITER Project, which is the next logical step in the development of fusion energy. The paper will describe ITER, its aims, its design, and the supporting manufacture of prototype components. The European contribution to ITER, the exploitation of the Joint European Torus (JET), and the long-term reactor technology R and D are carried out under the multilateral European Fusion Development Agreement (EFDA)

  13. RETROSPECTIVE RESEARCH ON REGRESSION PATTERN IN MALE SKELETAL EPIPHYSEAL FUSION

    Directory of Open Access Journals (Sweden)

    Ranga Rao

    2016-02-01

    Full Text Available In developing countries like India, because of illiteracy, ignorance regarding the importance of official records like birth and death, vast majority of population fail to give information of such vital events to the concerning authorities. This causes paucity in such information when needed in a medico-legal case or for research purpose. There is a wide confusion and controversy regarding the standard method to be used for estimating age in the Indian Sub-continent. The aim of the current study is to find the correlation among the various parameters of commonly examined ossification centres, through which a regression formula with positive correlation and maximum coefficient of determination can be, derived which can be attempted to be standardised for the estimation of age.

  14. Development of high yield strength non-magnetic steels for the equipments of nuclear fusion research

    International Nuclear Information System (INIS)

    Matsuoka, Hidenori; Mukai, Tetsuya; Ohtani, Hiroo; Tsuruki, Takanori; Okada, Yasutaka

    1979-01-01

    Recently, activity of nuclear fusion research and so forth increase the demand of non-magnetic materials for various equipments and structures. For these usage, very low magnetic permeability as well as high strength are required under high magnetic field. Based on fundamental research, middle C-17% Cr-7% Ni-N non-magnetic steel has been developed. The developed steel shows more stable austenite phase and possesses higher yield strength and endurance limit of more than 10 kg/mm 2 , compared with 18% Cr-8% Ni austenitic steel. Also the developed steel has good ductility and toughness in spite of the high yield strength and shows better machinability than usual high Mn non- magnetic steels. The large forgings of this newly developed steel are manufactured in the works for the equipments of nuclear fusion research and confirmed good mechanical properties, high fatigue strength and low permeability. (author)

  15. European Fusion Materials Research Program - Recent Results and Future Strategy

    International Nuclear Information System (INIS)

    Diegele, E.; Andreani, R.; Laesser, R.; Schaaf, B. van der

    2005-01-01

    The paper reviews the objectives and the status of the current EU long-term materials program. It highlights recent results, discusses some of the key issues and major existing problems to be resolved and presents an outlook on the R and D planned for the next few years. The main objectives of the Materials Development program are the development and qualification of reduced activation structural materials for the Test Blanket Modules (TBMs) in ITER and of low activation structural materials resistant to high fluence neutron irradiation for in-vessel components such as breeding blanket, divertor and first wall in DEMO. The EU strategy assumes: (i) ITER operation starting in 2015 with DEMO relevant Test Blanket Modules to be installed from day one of operation, (ii) IFMIF operation in 2017 and (iii) DEMO final design activities in 2022 to 2025. The EU candidate structural material EUROFER for TBMs has to be fully code qualified for licensing well before 2015. In parallel, research on materials for operation at higher temperatures is conducted following a logical sequence, by supplementing EUROFER with the oxide dispersion strengthened ferritic steels and, thereafter, with fibre-reinforced Silicon Carbide (SiC f /SiC). Complementary, tungsten alloys are developed as structural material for high temperature applications such as gas-cooled divertors

  16. Fusion Canada issue 10

    International Nuclear Information System (INIS)

    1990-02-01

    A short bulletin from the National Fusion Program. Included in this issue is a report on Fusion Materials Research, ITER physics research, fusion performance record at JET, and design options for reactor building. 4 figs

  17. Progress and status of fusion technology and materials research in China

    International Nuclear Information System (INIS)

    Xu Zengyu; Liu Xiang; Chen Jiming; Zhang Fu

    2003-01-01

    Fusion technology and materials research in China was included in the National High Technology Project during 1986-2000. Since 2000, the National Natural Science Foundation Committee, the State Development Planning Commission, and the Ministry of Science and Technology have supported this field of research. The research program has covered the topics of tritium engineering, plasma facing materials and structural materials. The Southwestern Institute of Physics has been a leading institute in this research program in the last 15 years in China, and over ten universities and institutes have joined the program. (author)

  18. EURATOM/UKAEA Association fusion research. 1998/99 progress report

    International Nuclear Information System (INIS)

    1999-11-01

    This annual progress report describes the fusion energy research carried out under the Contract of Association between UKAEA and the European atomic energy community, EURATOM: the EURATOM/UKAEA Fusion Association. It covers the period from April 1998 to March 1999, which has been a very active time, and has included contributions to the European Fusion Programme in several important areas. A main objective of the EURATOM/UKAEA Association is to provide support for JET, which is presently operated as a Joint Undertaking, but this will end in December 1999. It is proposed that the facilities will then pass to the UKAEA which will operate them for a programme of work by all the European Associations in support of ITER; UKAEA has been heavily involved in drafting the Implementing Agreement and operating contract with its European partners. There has also been a strong involvement in the JET scientific and technology programme which, following operation with tritium, includes activation studies and the impact of tritium retention. Highlights in the scientific programme included the first measurements of the plasma current density distribution in configurations with the potential for steady state operation. A second key objective is to contribute to the design of ITER, and in particular the RTO-ITER with its focus on a burning plasma of reduced size. ITER is the tokamak proposed to demonstrate the physics and many of the technology requirements for fusion power production, designed by Europe, Japan, the Russian Federation and the United States. Experiments on our COMPASS-D tokamak, which has the same geometry as JET and ITER, are supported by a strong theory programme to develop our understanding of key issues for ITER. One such issue is the study of instabilities which arise in the approach to a steady state configuration at high normalised plasma pressure, β, using micro-wave heating and current drive schemes. Data from our 'spherical' tokamak START, which ceased

  19. Developement of technologies for nuclear fusion at the Karlsruhe Research Center. Pt. 1

    International Nuclear Information System (INIS)

    Bahm, W.; Dammertz, G.; Glugla, M.; Janeschitz, G.; Komarek, P.; Mack, A.

    2002-01-01

    The planned ITER plant needs plasma heating powers of approx. 70-150 MW. Work performed at the Karlsruhe Research Center under this heading mainly comprises the development of microwave oscillators (gyrotrons) and their use for an electron cyclotron resonance heating system and for non-inductive plasma current operation. The plasma, which is approx. 100 million C hot, is confined in a 'magnetic cage' so as to avoid any contact with the wall structures of the vacuum vessel. Building up a magnetic field of this magnitude requires field strengths of at least 2-5 tesla in the plasma; field strengths of 11-13 tesla at the magnet coils are required for future fusion plants, such as ITER. Consequently, the development of the required future superconducting magnet coils enjoys high priority. The blanket, i.e. the enclosure around the combustion chamber of a fusion reactor, plays a major role in the design of a future fusion power plant. Blanket concepts meeting technical requirements are being developed and studied. A blanket must meet three requirements: It must convert the neutron energy into heat, breed the tritium fuel by nuclear reactions, and shield the magnets from neutron and gamma radiations. The fuel cycle of fusion reactors is determined by the gaseous phase of the two hydrogen isotopes, deuterium and tritium. In general, hydrogen handling technologies have been developed to a high level, but can be transferred to the handling of deuterium and radioactive tritium only to a very limited extent. Consequently, the necessary development work is carried out. The state of the plasma, also with respect to its purity, is a factor of special importance, as impurities will cause the plasma to dissolve and thus the fusion reaction to break down. Primary vacuum pumps, another area of activity of the Karlsruhe Research Center, first must evacuate the reactor vessel and then, during operation, maintain the necessary atmosphere. (orig.) [de

  20. Reducing risk and accelerating delivery of a neutron source for fusion materials research

    Energy Technology Data Exchange (ETDEWEB)

    Surrey, E., E-mail: Elizabeth.Surrey@ccfe.ac.uk [EURATOM/CCFE, Abingdon OX14 3DB (United Kingdom); Porton, M. [EURATOM/CCFE, Abingdon OX14 3DB (United Kingdom); Davenne, T.; Findlay, D.; Letchford, A.; Thomason, J. [STFC Rutherford Appleton Laboratory, Harwell OX11 0QX (United Kingdom); Roberts, S.G.; Marrow, J.; Seryi, A. [University of Oxford, Oxford OX1 3DP (United Kingdom); Connolly, B. [University of Birmingham, Edgbaston B15 2TT (United Kingdom); Owen, H. [University of Manchester, Manchester M13 9PL (United Kingdom)

    2014-04-15

    Highlights: • Proposed neutron source for fusion materials – FAFNIR – n(d,C) stripping source. • Near term technology, reduces risk compared with IFMIF, timely data production. • Technical, economic and programme needs assessed, compatible with EU Roadmap proposals. • Safety case impacts regulatory role for source, now mainly stakeholder insurance. - Abstract: The materials engineering database relevant to fusion irradiation is poorly populated and it has long been recognized that a fusion spectrum neutron source will be required, the facility IFMIF being the present proposal. Re-evaluation of the regulatory approach for the EU proposed DEMO device shows that the purpose of the source can be changed from lifetime equivalent irradiation exposure to data generation at lower levels of exposure by adopting a defence in depth strategy and regular component surveillance. This reduces the specification of the source with respect to IFMIF allowing lower risk technology solutions to be considered. A description of such a source, the Facility for Fusion Neutron Irradiation Research, FAFNIR, is presented here along with project timescales and costs.

  1. Research in the field of neutronics and nuclear data for fusion

    International Nuclear Information System (INIS)

    Batistoni, P.

    2001-01-01

    A reliable and validated nuclear database is required for the design of a fusion reactor. Neutrons produced by the fusion reactions between deuterium and tritium have a very peaked energy spectrum at 14 MeV, requiring a substantial extrapolation with respect to the database made available from fission studies. The correct evaluation of shielding properties, damage, nuclear heating and of tritium breeding performance in the blanket surrounding the reaction chamber is crucial to the correct reactor design. Moreover, the attractiveness of fusion relies in the low activation of the reactor components and in the minimal production of long-term radioactive waste that is pursued with development of low activation materials. Beside the materials development, Europe is carrying out a co-ordinated program for the development of adequate nuclear database and numerical tools, directed to evaluations, processing, application, and benchmarking of cross sections including uncertainty information. Experimental validation of data and of the relative uncertainties is also pursued, both on material samples and on more design-oriented experiments. A general view of the research work in the field of neutronics and nuclear data for fusion will be given in the presentation, with emphasis to the experimental validation activity.(author)

  2. Balanced program plan. Volume 10. Fusion: analysis for biomedical and environmental research

    International Nuclear Information System (INIS)

    Hungate, F.P.

    1976-06-01

    Development of the Balanced Program Plan for analysis for biomedical and environmental research was initiated in the spring of 1975. The goal was a redefinition of research efforts and priorities to meet ERDA's requirements for a program of health and environmental research to support the development and commercialization of energy technologies. As part of the Balanced Program planning effort the major ERDA-supported multidisciplinary laboratories were assigned responsibility for analyzing the research needs of each of nine energy technologies and describing a research program to meet these needs. The staff of the Division of Biomedical and Environmental Research was assigned the task of defining a research program addressed to each of five biomedical and environmental research categories (characterization, measurement and monitoring; physical and chemical processes and effects; health effects; ecological effects; and integrated assessment and socioeconomic processes and effects) applicable to all energy technologies. The first drafts of these documents were available for a work-shop in June 1975 at which the DBER staff and scientists from the laboratories developed a comprehensive set of program recommendations. Pacific Northwest Laboratory was assigned responsibility for defining research needs and a recommended research program for fusion and fission technologies. This report, Volume 10, presents the input for fusion

  3. Research Needs for Magnetic Fusion Energy Sciences. Report of the Research Needs Workshop (ReNeW) Bethesda, Maryland, June 8-12, 2009

    Energy Technology Data Exchange (ETDEWEB)

    None

    2009-06-08

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

  4. Extending the capabilities of the DIII-D Plasma Control System for worldwide fusion research collaborations

    International Nuclear Information System (INIS)

    Penaflor, B.G.; Ferron, J.R.; Walker, M.L.; Humphreys, D.A.; Leuer, J.A.; Piglowski, D.A.; Johnson, R.D.; Xiao, B.J.; Hahn, S.H.; Gates, D.A.

    2009-01-01

    This paper will discuss the recent enhancements which have been made to the DIII-D Plasma Control System (PCS) in order to further extend its usefulness as a shared tool for worldwide fusion research. The PCS developed at General Atomics is currently being used in a number of fusion research experiments worldwide, including the DIII-D Tokamak Facility in San Diego, and most recently the KSTAR Tokamak in South Korea. A number of enhancements have been made to support the ongoing needs of the DIII-D Tokamak in addition to meeting the needs of other PCS users worldwide. Details of the present PCS hardware and software architecture along with descriptions of the latest enhancements will be given.

  5. Spatially resolved soft x-ray diagnostics in fusion energy research

    International Nuclear Information System (INIS)

    Mlynar, J.; Weinzettl, V.; Imrisek, M.; Loeffelmann, V.

    2013-01-01

    With construction of ITER, the fusion community has progressed into a new stage of research with increased focus on reactor technologies. Corresponding development of diagnostic systems for fusion is required, including research of novel diagnostic methods, validation of radiation hard detectors, and tests of sensors for real-time operation and control, which comprise development of tools for fast data analyses. In parallel, diagnostic systems on running fusion experiments substantially contribute to better understanding of reactor-relevant plasma physics, in particular of energy confinement, plasma stability and transport of impurities. In this respect, spatially resolved Soft X-ray (SXR) diagnostic systems present an interesting case study of development towards reactor-relevant systems. In magnetic confinement fusion research, spatial distribution of SXR radiation with spectral range typically 1 keV - 15 keV is mostly measured by a photosensitive single-row semiconductor elements in a pinhole camera shielded by a beryllium foil. The SXR intensity strongly depends on plasma density, temperature and effective charge, which carry a valuable information on the plasma core physics. Data from SXR diagnostic can be also used for the operation control, among others due to their sensitivity to heavy impurity concentration or to the position of the peak temperature. In order to reconstruct the spatial distribution of SXR plasma emission from the measured line integrated signals, several tomographic methods have been developed and validated. However, the semiconductor elements cannot survive in harsh conditions of future fusion reactors due to radiation damage, which calls for development of radiation hard SXR cameras. In this contribution, role of the SXR diagnostics will be presented in experience and future plans of the Czech tokamak COMPASS (IPP Prague) and the French tokamak TORE SUPRA (CEA Cadarache). In IPP Prague, data from SXR cameras recently contributed to

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

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, W.B.

    1979-09-01

    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.

  7. Preliminary results from MBE-4: A four beam induction linac for heavy ion fusion research

    International Nuclear Information System (INIS)

    Fessenden, T.J.; Judd, D.L.; Keefe, D.; Kim, C.; Laslett, L.J.; Smith, L.; Warwick, A.I.; Warwick, P.b.A.I.

    1986-01-01

    Preliminary results are presented from a scaled experimental multiple beam induction linac. This experiment is part of a program of accelerator research for heavy ion fusion. It is shown that multiple beams can be accelerated without significant mutual interaction. Measurements of the longitudinal dynamics of a current-amplifying induction linac are presented and compared to calculations. Coupling of transverse and longitudinal dynamics is discussed

  8. A Scenario to Provide Atomic Data for Fusion Research in the Stage of Precision Physics

    International Nuclear Information System (INIS)

    Li Jiaming; Gao Xiang; Cheng Cheng; Zhang Xiaole; Qing Bo

    2010-01-01

    In order to provide abundant atomic data for fusion research in the stage of precision physics, a scenario, being a combination of indispensable theoretical calculations and bench-mark experimental measurements, is proposed. Such abundant atomic data are compiled mainly by theoretical calculations. Accuracies of such abundant data (i.e., atomic energy levels and corresponding cross sections) are ascertained only by a finite number of bench-mark experimental measurements based on analytical calculation of scattering matrices.

  9. Benefit-analysis of accomplishments from the magnetic fusion energy (MFE) research program

    International Nuclear Information System (INIS)

    Lago, A.M.; Weinblatt, H.; Hamilton, E.E.

    1987-01-01

    This report presents the results of a study commissioned by the US Department of Energy's (DOE) Office of Program Analysis to examine benefits from selected accomplishments of DOE's Magnetic Fusion Energy (MFE) Research Program. The study objectives are presented. The MFE-induced innovation and accomplishments which were studied are listed. Finally, the benefit estimation methodology used is described in detail. The next seven chapters document the results of benefit estimation for the MFE accomplishments studied

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

    International Nuclear Information System (INIS)

    Boyer, W.B.

    1979-09-01

    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

  11. Preliminary results from MBE-4: a four beam induction linac for heavy ion fusion research

    International Nuclear Information System (INIS)

    Fessenden, T.J.; Judd, D.L.; Keefe, D.; Kim, C.; Laslett, L.J.; Smith, L.; Warwick, A.I.

    1986-05-01

    Preliminary results are presented from a scaled experimental multiple beam induction linac. This experiment is part of a program of accelerator research for heavy ion fusion. It is shown that multiple beams can be accelerated without significant mutual interaction. Measurements of the longitudinal dynamics of a current-amplifying induction linac are presented and compared to calculations. Coupling of transverse and longitudinal dynamics is discussed

  12. Collision excitation studies useful for plasma diagnostics in astrophysics and fusion research

    International Nuclear Information System (INIS)

    Man Mohan; Aggarwal, Sunny

    2015-01-01

    The urgent research for energy sources has led many countries to collaborate on demonstrating the scientific and technological feasibility of magnetic fusion through the construction of International Thermonuclear Experimental Reactor in France. Data on highly charged ions with high Z will be important in this quest. Atomic data such as energy levels, radiative rates and collision excitation plays an important role in fusion research and extensive knowledge of atomic parameters is needed for plasma diagnostics. There is a very limited knowledge so far about the heavy atoms due to involvement of strong relativistic effects. For heavy atoms, electron correlation effects and relativistic effects are strongly coupled making it necessary to use a relativistic theory which also incorporates 'electron correlations effects on the same footing. For treating heavy atoms there have been new developments and many codes in the relativistic domain have been developed by various authors. Among them, multi-configuration Hartree (Dirac) Fock (MCDF) model based codes have been found very useful in ab-initio investigations. We have calculated the energy levels, radiative rates and lifetimes for heavy charged F, Na and Mg like tungsten ions using MCDF and FAC and compared our results with the other available theoretical and experimental results. Also, we have performed collision excitation calculations for F, Na and Mg like tungsten ions which will be useful for astrophysical and fusion, plasma. Also, we have compared our collision excitation results with distorted wave calculations and they are found to be in good agreement. The main goal of this paper is to provide useful atomic physics data for use in fusion research and in astrophysical and industrial plasmas. (author)

  13. Plasma Physics and Controlled Nuclear Fusion Research. Vol. II. Proceedings of a Conference on Plasma Physics and Controlled Physics Research

    International Nuclear Information System (INIS)

    1966-01-01

    Research on controlled nuclear fusion was first disclosed at the Second United Nations Conference on the Peaceful Uses of Atomic Energy, held at Geneva in 1958. From the information given, it was evident that a better understanding of the behaviour of hot dense plasmas was needed before the goal of economic energy release from nuclear fusion could be reached. The fact that research since then has been most complex and costly has enhanced the desirability of international co-operation and exchange of information and experience. Having organized its First Conference on Plasma Physics and Controlled Nuclear Fusion Research at Salzburg in 1961, the International Atomic Energy Agency again provided the means for such cooperation in organizing its Second Conference on this subject on 6-10 September, 1965, at Culham, Abingdon, Berks, England. The meeting was arranged with the generous help of the United Kingdom Atomic Energy Authority at their Culham Laboratory, where the facilities and assistance of the staff were greatly appreciated. At the meeting, which was attended by 268 participants from 26 member states and three international organizations, significant results from many experiments, including those from the new and larger machines, became available. It has now become feasible to intercorrelate data obtained from a number of similar machines; this has led to a more complete understanding of plasma behaviour. No breakthrough was reported nor had been expected towards the economical release of the energy from fusion, but there was increased understanding of the problems of production, control and containment of high-density and high-temperature plasmas

  14. Panel discussion: Progress and plans for magnetic fusion: Summary of comments on recent progress in fusion research at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Sheffield, J.

    1989-01-01

    Progress in fusion research is marked not so much by a few giant steps as by a continual number of small steps, which yield a steady advance toward the goal of producing a fusion reactor. During the past year, there have been two such steps in the Oak Ridge National Laboratory (ORNL) program: the experimental demonstration of access to the second stable region of beta in the Advanced Toroidal Facility (ATF); and the acceleration of a frozen hydrogen pellet by an intense electron beam. This paper discusses these steps

  15. Fusion neutronics

    CERN Document Server

    Wu, Yican

    2017-01-01

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

  16. Fusion Physics

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-09-15

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

  17. US Heavy Ion Beam Research for Energy Density Physics Applications and Fusion

    International Nuclear Information System (INIS)

    Davidson, R.C.; Logan, B.G.; Barnard, J.J.; Bieniosek, F.M.; Briggs, R.J.; Callahan D.A.; Kireeff Covo, M.; Celata, C.M.; Cohen, R.H.; Coleman, J.E.; Debonnel, C.S.; Grote, D.P.; Efthimiom, P.C.; Eylon, S.; Friedman, A.; Gilson, E.P.; Grisham, L.R.; Henestroza, E.; Kaganovich, I.D.; Kwan, J.W.; Lee, E.P.; Lee, W.W.; Leitner, M.; Lund, S.M.; Meier, W.R.; Molvik, A.W.; Olson, C.L.; Penn, G.E.; Qin, H.; Roy, P.K.; Rose, D.V.; Sefkow, A.; Seidl, P.A.; Sharp, W.M.; Startsev, E.A.; Tabak, M.; Thoma, C.; Vay, J-L; Wadron, W.L.; Wurtele, J.S.; Welch, D.R.; Westenskow, G.A.; Yu, S.S.

    2005-01-01

    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

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

    International Nuclear Information System (INIS)

    Davidson, R.C.; Logan, B.G.; Barnard, J.J.; Bieniosek, F.M.; Briggs, R.J.

    2005-01-01

    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

  19. Research on Degeneration Model of Neural Network for Deep Groove Ball Bearing Based on Feature Fusion

    Directory of Open Access Journals (Sweden)

    Lijun Zhang

    2018-02-01

    Full Text Available Aiming at the pitting fault of deep groove ball bearing during service, this paper uses the vibration signal of five different states of deep groove ball bearing and extracts the relevant features, then uses a neural network to model the degradation for identifying and classifying the fault type. By comparing the effects of training samples with different capacities through performance indexes such as the accuracy and convergence speed, it is proven that an increase in the sample size can improve the performance of the model. Based on the polynomial fitting principle and Pearson correlation coefficient, fusion features based on the skewness index are proposed, and the performance improvement of the model after incorporating the fusion features is also validated. A comparison of the performance of the support vector machine (SVM model and the neural network model on this dataset is given. The research shows that neural networks have more potential for complex and high-volume datasets.

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  1. Research and Development of Landmine Detection System by a Compact Fusion Neutron Source

    International Nuclear Information System (INIS)

    Yoshikawa, Kiyoshi; Masuda, Kai; Toku, Hisayuki; Nagasaki, Kazunobu; Mizutani, Toshiyuki; Takamatsu, Teruhisa; Imoto, Masaki; Yamamoto, Yasushi; Ohnishi, Masami; Osawa, Hodaka; Hotta, Eiki; Kohno, Toshiyuki; Okino, Akitoshi; Watanabe, Masato; Yamauchi, Kunihito; Yuura, Morimasa; Shiroya, Seiji; Misawa, Tsuyoshi; Mori, Takamasa

    2005-01-01

    Current results are described on the research and development of an advanced anti-personnel landmine detection system by using a compact discharge-type fusion neutron source called IECF (Inertial-Electrostatic Confinement Fusion). Landmines are to be identified through backscattering of neutrons, and specific-energy capture γ-rays by hydrogen and nitrogen atoms in the landmine explosives.For this purpose, improvements in the IECF were made by various methods to achieve a drastic enhancement of neutron yields of more than 10 8 n/s in pulsed operation. This required R and D on the power source, as well as analysis of envisaged detection systems with multi-sensors. The results suggest promising and practical features for humanitarian landmine detection, particularly, in Afghanistan

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

    International Nuclear Information System (INIS)

    1990-12-01

    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

  3. Evaluation of laser-driven ion energies for fusion fast-ignition research

    Science.gov (United States)

    Tosaki, S.; Yogo, A.; Koga, K.; Okamoto, K.; Shokita, S.; Morace, A.; Arikawa, Y.; Fujioka, S.; Nakai, M.; Shiraga, H.; Azechi, H.; Nishimura, H.

    2017-10-01

    We investigate laser-driven ion acceleration using kJ-class picosecond (ps) laser pulses as a fundamental study for ion-assisted fusion fast ignition, using a newly developed Thomson-parabola ion spectrometer (TPIS). The TPIS has a space- and weight-saving design, considering its use in an laser-irradiation chamber in which 12 beams of fuel implosion laser are incident, and, at the same time, demonstrates sufficient performance with its detectable range and resolution of the ion energy required for fast-ignition research. As a fundamental study on laser-ion acceleration using a ps pulse laser, we show proton acceleration up to 40 MeV at 1 × 10^{19} W cm^{-2}. The energy conversion efficiency from the incident laser into protons higher than 6 MeV is 4.6%, which encourages the realization of fusion fast ignition by laser-driven ions.

  4. Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Nishi, Masataka; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Isobe, Kanetsugu; O'Hira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Suzuki, Takumi; Yamada, Masayuki; Konishi, Satoshi

    2000-01-01

    The Tritium Process Laboratory (TPL) at the Japan Atomic Energy Research Institute has been working on the development of fuel processing technology for fusion reactors as a major activity. A fusion fuel processing loop was installed and is being tested with tritium under reactor relevant conditions. The loop at the TPL consists of ZrCo based tritium storage beds, a plasma exhaust processing system using a palladium diffuser and an electrolytic reactor, cryogenic distillation columns for isotope separation, and analytical systems based on newly developed micro gas chromatographs and Raman Spectroscopy. Several extended demonstration campaigns were performed under realistic reactor conditions to test tritiated impurity processing. A sophisticated control technique of distillation column was performed at the same time, and integrated fuel circulation was successfully demonstrated. Major recent design work on the International Thermonuclear Experimental Reactor (ITER) tritium plant at the TPL is devoted to water detritiation based on liquid phase catalytic exchange for improved tritium removal from waste water

  5. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    Science.gov (United States)

    Rieth, M.; Dudarev, S. L.; Gonzalez de Vicente, S. M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D. E. J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W. W.; Battabyal, M.; Becquart, C. S.; Blagoeva, D.; Boldyryeva, H.; Brinkmann, J.; Celino, M.; Ciupinski, L.; Correia, J. B.; De Backer, A.; Domain, C.; Gaganidze, E.; García-Rosales, C.; Gibson, J.; Gilbert, M. R.; Giusepponi, S.; Gludovatz, B.; Greuner, H.; Heinola, K.; Höschen, T.; Hoffmann, A.; Holstein, N.; Koch, F.; Krauss, W.; Li, H.; Lindig, S.; Linke, J.; Linsmeier, Ch.; López-Ruiz, P.; Maier, H.; Matejicek, J.; Mishra, T. P.; Muhammed, M.; Muñoz, A.; Muzyk, M.; Nordlund, K.; Nguyen-Manh, D.; Opschoor, J.; Ordás, N.; Palacios, T.; Pintsuk, G.; Pippan, R.; Reiser, J.; Riesch, J.; Roberts, S. G.; Romaner, L.; Rosiński, M.; Sanchez, M.; Schulmeyer, W.; Traxler, H.; Ureña, A.; van der Laan, J. G.; Veleva, L.; Wahlberg, S.; Walter, M.; Weber, T.; Weitkamp, T.; Wurster, S.; Yar, M. A.; You, J. H.; Zivelonghi, A.

    2013-01-01

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

  6. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    International Nuclear Information System (INIS)

    Rieth, M.; Dudarev, S.L.; Gonzalez de Vicente, S.M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D.E.J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W.W.; Battabyal, M.; Becquart, C.S.; Blagoeva, D.; Boldyryeva, H.

    2013-01-01

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme’s main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

  7. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Rieth, M., E-mail: Michael.rieth@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Dudarev, S.L. [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Gonzalez de Vicente, S.M. [EFDA-Close Support Unit, Garching (Germany); Aktaa, J. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Ahlgren, T. [University of Helsinki, Department of Physics, Helsinki (Finland); Antusch, S. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Armstrong, D.E.J. [Department of Materials, University of Oxford (United Kingdom); Balden, M. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Garching (Germany); Baluc, N. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Barthe, M.-F. [CNRS, UPR3079 CEMHTI, 1D Avenue, de la Recherche Scientifique, 45071 Orleans cedex 2 (France); Universite d' Orleans, Polytech ou Faculte des Sciences, Avenue du Parc Floral, BP 6749, 45067 Orleans cedex 2 (France); Basuki, W.W. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Battabyal, M. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Becquart, C.S. [Unite Materiaux et Transformations, UMR 8207, 59655 Villeneuve d' Ascq (France); Blagoeva, D. [NRG, Nuclear Research and consultancy Group, Petten (Netherlands); Boldyryeva, H. [Institute of Plasma Physics, Za Slovankou 3, 18200 Praha (Czech Republic); and others

    2013-01-15

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

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

    International Nuclear Information System (INIS)

    1988-12-01

    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

  9. Heavy Ion Fusion Accelerator Research (HIFAR) year-end report, October 1, 1987--March 31, 1988

    International Nuclear Information System (INIS)

    1988-06-01

    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 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 beams; and final bunching, transport, and accurate focusing on a small target

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

    International Nuclear Information System (INIS)

    Johnson, R.K.; Bouret, C.

    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. Integrated Approach to Dense Magnetized Plasmas Applications in Nuclear Fusion Technology. Report of a Coordinated Research Project 2007-2011

    International Nuclear Information System (INIS)

    2013-04-01

    Through its coordinated research activities, the IAEA promotes the development and application of nuclear technologies in Member States. The scientific and technical knowledge required for the construction and operation of large nuclear fusion research facilities, including ITER and the Laser Megajoule in France, and the Z machine and the National Ignition Facility in the United States of America, necessitates several accompanying research and development programmes in physics and technology. This is particularly true in the areas of materials science and fusion technology. Hence, the long standing IAEA effort to conduct coordinated research projects (CRPs) in these areas is aimed at: (i) the development of appropriate technical tools to investigate the issue of materials damage and degradation in a fusion plasma environment; and (ii) the emergence of a knowledge based understanding of the various processes underlying materials damage and degradation, thereby leading to the identification of suitable candidate materials fulfilling the stringent requirements of a fusion environment in any next step facility. Dense magnetized plasma (DMP) devices serve as a first test bench for testing of fusion relevant plasma facing materials, diagnostic development and calibration, technologies and scaling to conceptual principles of larger devices while sophisticated testing facilities such as the International Fusion Materials Irradiation Facility (IFMIF) are being designed. The CRP on Integrated Approach to Dense Magnetized Plasmas Applications in Nuclear Fusion Technology described herein was initiated in 2007 with the participation of 12 research institutions in 8 Member States and was concluded in 2011. It was designed with specific research objectives falling into two main categories: support to mainstream fusion research and development of DMP technology. This publication is a compilation of the individual reports submitted by the 12 CRP participants. These reports discuss

  12. Fusion of smart, multimedia and computer gaming technologies research, systems and perspectives

    CERN Document Server

    Favorskaya, Margarita; Jain, Lakhmi; Howlett, Robert

    2015-01-01

      This monograph book is focused on the recent advances in smart, multimedia and computer gaming technologies. The Contributions include:   ·         Smart Gamification and Smart Serious Games. ·         Fusion of secure IPsec-based Virtual Private Network, mobile computing and rich multimedia technology. ·         Teaching and Promoting Smart Internet of Things Solutions Using the Serious-game Approach. ·         Evaluation of Student Knowledge using an e-Learning Framework. ·         The iTEC Eduteka. ·         3D Virtual Worlds as a Fusion of Immersing, Visualizing, Recording, and Replaying Technologies. ·         Fusion of multimedia and mobile technology in audioguides for Museums and Exhibitions: from Bluetooth Push to Web Pull. The book is directed to researchers, students and software developers working in the areas of education and information technologies.  

  13. Role of Radio Frequency and Microwaves in Magnetic Fusion Plasma Research

    Directory of Open Access Journals (Sweden)

    Hyeon K. Park

    2017-10-01

    Full Text Available The role of electromagnetic (EM waves in magnetic fusion plasma—ranging from radio frequency (RF to microwaves—has been extremely important, and understanding of EM wave propagation and related technology in this field has significantly advanced magnetic fusion plasma research. Auxiliary heating and current drive systems, aided by various forms of high-power RF and microwave sources, have contributed to achieving the required steady-state operation of plasmas with high temperatures (i.e., up to approximately 10 keV; 1 eV = 10000 K that are suitable for future fusion reactors. Here, various resonance values and cut-off characteristics of wave propagation in plasmas with a nonuniform magnetic field are used to optimize the efficiency of heating and current drive systems. In diagnostic applications, passive emissions and active sources in this frequency range are used to measure plasma parameters and dynamics; in particular, measurements of electron cyclotron emissions (ECEs provide profile information regarding electron temperature. Recent developments in state-of-the-art 2D microwave imaging systems that measure fluctuations in electron temperature and density are largely based on ECE. The scattering process, phase delays, reflection/diffraction, and the polarization of actively launched EM waves provide us with the physics of magnetohydrodynamic instabilities and transport physics.

  14. Developing a plasma focus research training system for the fusion energy age

    International Nuclear Information System (INIS)

    Lee, S.

    2014-01-01

    The 3 kJ UNU/ICTP Plasma Focus Facility is the most significant device associated with the AAAPT (Asian African Association for Plasma Training). In original and modified/upgraded form it has trained generations of plasma focus (PF) researchers internationally, producing many PhD theses and peer-reviewed papers. The Lee Model code was developed for the design of this PF. This code has evolved to cover all PF machines for design, interpretation and optimization, for derivation of radiation scaling laws; and to provide insights into yield scaling limitations, radiative collapse, speed-enhanced and current-stepped PF variants. As example of fresh perspectives derivable from this code, this paper presents new results on energy transfers of the axial and radial phases of generalized PF devices. As the world moves inexorably towards the Fusion Energy Age it becomes ever more important to train plasma fusion researchers. A recent workshop in Nepal shows that demand for such training continues. Even commercial project development consultants are showing interest. We propose that the AAAPT-proven research package be upgraded, by modernizing the small PF for extreme modes of operation, switchable from the typical strong-focus mode to a slow-mode which barely pinches, thus producing a larger, more uniform plasma stream with superior deposition properties. Such a small device would be cost-effective and easily duplicated, and have the versatility of a range of experiments from intense multi-radiation generation and target damage studies to superior advanced-materials deposition. The complementary code is used to reference experiments up to the largest existing machine. This is ideal for studying machine limitations and scaling laws and to suggest new experiments. Such a modernized versatile PF machine complemented by the universally versatile code would extend the utility of the PF experience; so that AAAPT continues to provide leadership in pulsed plasma research training in

  15. Atomic data for heavy element impurities in fusion reactors. Summary report of first IAEA research co-ordination meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2006-01-01

    Twelve international experts discussed in detail the properties of heavy elements relevant to fusion energy research participated at the first Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Atomic data for heavy element impurities in fusion reactors' at IAEA Headquarters on 14-15 November 2005. The participants summarized all recent relevant developments in their research efforts. Detailed discussions took place to formulate specific objectives for the CRP. From a list of data needs and a review of current research capabilities, a detailed work plan was formulated for the first phase of the CRP. The discussions, conclusions and recommendations of the RCM are briefly described in this report. (author)

  16. Balanced biomedical program plan. Volume X. Fusion analysis for and environmental research

    Energy Technology Data Exchange (ETDEWEB)

    1976-06-01

    In this draft planning document for health and environmental research needs relevant to the development of fusion technology, an attempt is made to integrate input from the participating laboratories on the basis of the King-Muir study categories. The general description covers only those concepts and features that are considered important to an understanding of possible and probable effects of thermonuclear reactors on health and the environment. Appendixes are included which reflect an understanding of three areas of special interest: materials requirements, effects from magnetic fields, and tritium effects.

  17. Program for development of toroidal superconducting magnets for fusion research, May 1975

    International Nuclear Information System (INIS)

    Long, H.M.; Lubell, M.S.

    1975-11-01

    The objective of this program is a tested magnet design which demonstrates the suitability and reliability needed to qualify toroidal superconducting magnets for fusion research devices in a time compatible with the D-T burning experiments time frame. The overall applied development program including tasks, manpower, and cost estimates is detailed here, but for the full toroidal system only the cost and time frame are outlined to show compatibility with the present program. The details of the full toroidal system fall under major device fabrication and will be included in a subsequent document

  18. Balanced biomedical program plan. Volume X. Fusion analysis for and environmental research

    International Nuclear Information System (INIS)

    1976-06-01

    In this draft planning document for health and environmental research needs relevant to the development of fusion technology, an attempt is made to integrate input from the participating laboratories on the basis of the King-Muir study categories. The general description covers only those concepts and features that are considered important to an understanding of possible and probable effects of thermonuclear reactors on health and the environment. Appendixes are included which reflect an understanding of three areas of special interest: materials requirements, effects from magnetic fields, and tritium effects

  19. Design and testing of the 2 MV heavy ion injector for the Fusion Energy Research Program

    International Nuclear Information System (INIS)

    Abraham, W.; Benjegerdes, R.; Reginato, L.; Stoker, J.; Hipple, R.; Peters, C.; Pruyn, J.; Vanecek, D.; Yu, S.

    1995-04-01

    The Fusion Energy Research Group at the Lawrence Berkeley Laboratory has constructed and tested a pulsed 2 MV injector that produces a driver size beam of potassium ions. This paper describes the engineering aspects of this development which were generated in a closely coupled effort with the physics staff. Details of the ion source and beam transport physics are covered in another paper at this conference. This paper discusses the design details of the pulse generator, the ion source, the extractor, the diode column, and the electrostatic quadrupole column. Included will be the test results and operating experience of the complete injector

  20. Characterization of Size, Composition and Origins of Dust in Fusion Devices. Summary Report of the Second Research Coordination Meeting

    International Nuclear Information System (INIS)

    Braams, B.J.; Skinner, C.H.

    2010-11-01

    Eleven experts on processes of dust in fusion experiments met for the 2nd Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Characterization of size, composition and origins of dust in fusion devices' held at IAEA Headquarters 21-23 June 2010. Participants summarized their studies on dust in fusion experiments and reviewed progress made since the first RCM. Gaps in knowledge were identified and a plan of work for the remainder of the CRP was developed. Presentations, discussions and recommendations of the RCM are summarized in this report. Eleven experts on processes of dust in fusion experiments met for the 2nd Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Characterization of size, composition and origins of dust in fusion devices' held at IAEA Headquarters 21-23 June 2010. Participants summarized their studies on dust in fusion experiments and reviewed progress made since the first RCM. Gaps in knowledge were identified and a plan of work for the remainder of the CRP was developed. Presentations, discussions and recommendations of the RCM are summarized in this report. (author)

  1. Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials

    International Nuclear Information System (INIS)

    Dalle Donne, M.

    1993-12-01

    As shown by recent developments beryllium has become one of the most important materials in the development of fusion reactors. It is practically the only neutron multiplier available for blankets with ceramic breeder materials and can be used with liquid metal breeders as well. It is one of the most likely materials to be used on the surface of the first walls and of the divertor. The neutron irradiation behavior of beryllium in a fusion reactor is not well know. Beryllium was extensively irradiated about 25-40 years ago and has been used since then in material testing reactors as reflector. In the meantime, however, beryllium has been improved quite considerably. Today it is possible to obtain commercially beryllium which is much more isotropic and contains smaller ammounts of oxide. There are already indications that these new kinds of beryllium behave better under irradiation. (orig.)

  2. Fusion breeder

    International Nuclear Information System (INIS)

    Moir, R.W.

    1982-01-01

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

  3. Characterization of size, composition and origins of dust in fusion devices. Summary report of the 1. research coordination meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2009-03-01

    Nine experts on dust formation and their physical and behavioural characteristics attended the first Research Coordination Meeting (RCM) on Characterization of Size, Composition and Origins of Dust in Fusion Devices held at IAEA Headquarters on 10-12 December 2008. Participants summarized recent relevant developments related to dust in fusion devices. The specific objectives of the CRP and a detailed work plan were formulated. Discussions, conclusions and recommendations of the RCM are briefly described in this report. (author)

  4. An archival study on the fusion researches in Japan from 1965 to 1986. An interview with Sekiguchi Tadashi

    International Nuclear Information System (INIS)

    Nisio, Sigeko; Uematsu, Eisui

    2001-12-01

    We here report an archival study undertaken by the method of an interview with Sekiguchi Tadashi, Professor Emeritus at the University of Tokyo. The theme covers the circumstances of the fusion research during the period (1965-1976) when fusion project was launched in Japan, and during the period (1970-1986) when JT-60 was initiated and subsequently developed. This interview was arranged as a part of the collaborative works organized with the Data and Planning Center of NIFS since 1999. (author)

  5. Fusion devices

    International Nuclear Information System (INIS)

    Fowler, T.K.

    1977-01-01

    Three types of thermonuclear fusion devices currently under development are reviewed for an electric utilities management audience. Overall design features of laser fusion, tokamak, and magnetic mirror type reactors are described and illustrated. Thrusts and trends in current research on these devices that promise to improve performance are briefly reviewed. Twenty photographs and drawings are included

  6. Report of 6th research meeting on basic process of fuel cycle for nuclear fusion reactors, Yayoi Research Group; 3rd expert committee on research of nuclear fusion fuel material correlation basis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    In this report, the lecture materials of Yayoi Research Group, 6th research meeting on basic process of fuel cycle for nuclear fusion reactors which was held at the University of Tokyo on March 25, 1996, are collected. This workshop was held also as 3rd expert committee on research of nuclear fusion fuel material correlation basis of Atomic Energy Society of Japan. This workshop has the character of the preparatory meeting for the session on `Interface effect in nuclear fusion energy system` of the international workshop `Interface effect in quantum energy system`, and 6 lectures and one comment were given. The topics were deuterium transport in Mo under deuterium ion implantation, the change of the stratum structure of graphite by hydrogen ion irradiation, the tritium behavior in opposing materials, the basic studies of the irradiation effects of solid breeding materials, the research on the behavior of hydroxyl group on the surface of solid breeding materials, the sweep gas effect on the surface of solid breeding materials, and the dynamic behavior of ion-implanted deuterium in proton-conductive oxides. (K.I.)

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

    International Nuclear Information System (INIS)

    Masaike, Akira

    2000-01-01

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

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

    International Nuclear Information System (INIS)

    Barnard, J.J.; Ahle, L.E.; Baca, D.; Bangerter, R.O.; Bieniosek, F.M.; Celata, C.M.; Chacon-Golcher, E.; Davidson, R.C.; Faltens, A.; Friedman, A.; Franks, R.M.; Grote, D.P.; Haber, I.; Henestroza, E.; Hoon, M.J.L. de; Kaganovich, I.; Karpenko, V.P.; Kishek, R.A.; Kwan, J.W.; Lee, E.P.; Logan, B.G.; Lund, S.M.; Meier, W.R.; Molvik, A.W.; Olson, C.; Prost, L.R.; Qin, H.; Rose, D.; Sabbi, G.-L.; Sangster, T.C.; Seidl, P.A.; Sharp, W.M.; Shuman, D.; Vay, J.-L.; Waldron, W.L.; Welch, D.; Yu, S.S.

    2001-01-01

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-01

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

  10. Collection of summaries of reports on result of research at basic experiment device for nuclear fusion reactor blanket design, 1995

    International Nuclear Information System (INIS)

    1996-07-01

    This report meeting was held on May 22, 1995 at University of Tokyo by about 40 participants. As the topics on the fusion reactor engineering research in Japan, lectures were given on the present state and future of nuclear fusion networks and on the strong magnetic field tokamak using electromagnetic force-balanced coils being planned. Thereafter, the reports of the results of the researches which were carried out by using this experimental facility were made, centering around the subject related to the future conception 'The interface properties of fusion reactor materials and particle transport control'. The publication was made on the future conception of the basic experiment setup for fusion reactor blanket design, the application of high temperature superconductors to the advancement of nuclear fusion reactors, the modeling of the dynamic irradiation behavior of fusion reactor materials, the interface particle behavior in plasma-wall interaction, the behavior of tritium on the surface of breeding materials, and breeding materials and the behavior of tritium in plasma-wall interaction. (K.I.)

  11. RO5: proposal of a relevant facility in nuclear fusion research

    International Nuclear Information System (INIS)

    Pouzo, J.

    1987-01-01

    The RO5 project is a proposal of an experiment in nuclear fusion research based in a plasma focus device. The main research scopes of the experiment, with respect to the scaling law foundations and the identification of the main nuclear reaction mechanisms, are discussed. A practical aim of the experiment is to reach 10 14 - 10 15 neutrons/pulse from D-D reactions in the plasma focus using a 3 MJ capacitor bank. It represents an energy efficience of around a 5% when D-T mixture is used as filling gas in the reactor (RO5 = Reactor of 5% in energy efficience). A first RO5 design obtained with a 2D snowplow model and taken into account the operation limits recently found, is presented. (author) [pt

  12. Report of the 1991 workshop on particle-material interactions for fusion research

    International Nuclear Information System (INIS)

    1992-11-01

    The Annual Workshop on Particle-Material Interactions in the Working Group of the Research Committee on A and M Data was held at the head-quarters of JAERI, Tokyo, on December 12-13, 1991. The purpose of the Workshop was to obtain future prospects for the activities of the Working Group, by discussing current states and problems in the research on particle-material interactions relevant to the thermocontrolled fusion. The present report contains 16 papers presented at the Workshop, which are mainly concerned with plasma-facing materials in ITER, radiation damage in carbon materials, trapping, emission and permeation of hydrogen in metals, and heavy ion-solid surface interactions. (author)

  13. Web-based (HTML5) interactive graphics for fusion research and collaboration

    Energy Technology Data Exchange (ETDEWEB)

    Kim, E.N., E-mail: kimny@fusion.gat.com [General Atomics, P.O. Box 85608, San Diego, CA (United States); Schissel, D.P.; Abla, G.; Flanagan, S.; Lee, X. [General Atomics, P.O. Box 85608, San Diego, CA (United States)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Interactive data visualization is supported via the Web without a browser plugin and provides users easy, real-time access to data of different types from various locations. Black-Right-Pointing-Pointer Crosshair, zoom, pan as well as toggling dimensionality and a slice bar for multi-dimensional data are available. Black-Right-Pointing-Pointer Data with PHP API can be applied: MDSplus and SQL have been tested. Black-Right-Pointing-Pointer Modular in design, this has been deployed to support both the experimental and the simulation research arenas. - Abstract: With the continuing development of web technologies, it is becoming feasible for websites to operate a lot like a scientific desktop application. This has opened up more possibilities for utilizing the web browser for interactive scientific research and providing new means of on-line communication and collaboration. This paper describes the research and deployment for utilizing these enhanced web graphics capabilities on the fusion research tools which has led to a general toolkit that can be deployed as required. It allows users to dynamically create, interact with and share with others, the large sets of data generated by the fusion experiments and simulations. Hypertext Preprocessor (PHP), a general-purpose scripting language for the Web, is used to process a series of inputs, and determine the data source types and locations to fetch and organize the data. Protovis, a Javascript and SVG based web graphics package, then quickly draws the interactive graphs and makes it available to the worldwide audience. This toolkit has been deployed to both the simulation and experimental arenas. The deployed applications will be presented as well as the architecture and technologies used in producing the general graphics toolkit.

  14. Web-based (HTML5) interactive graphics for fusion research and collaboration

    International Nuclear Information System (INIS)

    Kim, E.N.; Schissel, D.P.; Abla, G.; Flanagan, S.; Lee, X.

    2012-01-01

    Highlights: ► Interactive data visualization is supported via the Web without a browser plugin and provides users easy, real-time access to data of different types from various locations. ► Crosshair, zoom, pan as well as toggling dimensionality and a slice bar for multi-dimensional data are available. ► Data with PHP API can be applied: MDSplus and SQL have been tested. ► Modular in design, this has been deployed to support both the experimental and the simulation research arenas. - Abstract: With the continuing development of web technologies, it is becoming feasible for websites to operate a lot like a scientific desktop application. This has opened up more possibilities for utilizing the web browser for interactive scientific research and providing new means of on-line communication and collaboration. This paper describes the research and deployment for utilizing these enhanced web graphics capabilities on the fusion research tools which has led to a general toolkit that can be deployed as required. It allows users to dynamically create, interact with and share with others, the large sets of data generated by the fusion experiments and simulations. Hypertext Preprocessor (PHP), a general-purpose scripting language for the Web, is used to process a series of inputs, and determine the data source types and locations to fetch and organize the data. Protovis, a Javascript and SVG based web graphics package, then quickly draws the interactive graphs and makes it available to the worldwide audience. This toolkit has been deployed to both the simulation and experimental arenas. The deployed applications will be presented as well as the architecture and technologies used in producing the general graphics toolkit.

  15. Research and development of a compact fusion neutron source for humanitarian landmine detection

    International Nuclear Information System (INIS)

    Yoshikawa, K.; Masuda, K.; Yamamoto, Y.; Takamatsu, T.; Toku, H.; Nagasaki, K.; Hotta, E.; Yamauchi, K.; Ohnishi, M.; Osawa, H.

    2005-01-01

    Research and development of the advanced anti-personnel landmine detection system by using a compact discharge-type D-D fusion neutron source called IECF (Inertial-Electrostatic Confinement Fusion) are described. Landmines are to be identified through increased backscattering of neutrons by the hydrogen atoms, and specific-energy capture γ-ray emission by hydrogen and nitrogen atoms with thermalized neutrons in the landmine explosives. For this purpose, improvements of the IECF device were studied for drastic enhancement of neutron production rates of more than 10 8 n/s in pulsed operation including R and D of robust power sources, as well as analyses of envisaged detection system with multi-sensors in parallel in order to show promising and practical features of this detection system for humanitarian landmine detection, particularly, in the aridic, or dry Afghanistan deserted area, where the soil moisture remains between 3-8%, which eventually enables effectively detection of hydrogen anomaly inherent in the landmine explosives. In this paper, improvements of the IECF are focused to be described. (author)

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

    International Nuclear Information System (INIS)

    1989-06-01

    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

  17. Survey of Laser Markets Relevant to Inertial Fusion Energy Drivers, information for National Research Council

    International Nuclear Information System (INIS)

    Bayramian, A.J.; Deri, R.J.; Erlandson, A.C.

    2011-01-01

    Development of a new technology for commercial application can be significantly accelerated by leveraging related technologies used in other markets. Synergies across multiple application domains attract research and development (R and D) talent - widening the innovation pipeline - and increases the market demand in common components and subsystems to provide performance improvements and cost reductions. For these reasons, driver development plans for inertial fusion energy (IFE) should consider the non-fusion technology base that can be lveraged for application to IFE. At this time, two laser driver technologies are being proposed for IFE: solid-state lasers (SSLs) and KrF gas (excimer) lasers. This document provides a brief survey of organizations actively engaged in these technologies. This is intended to facilitate comparison of the opportunities for leveraging the larger technical community for IFE laser driver development. They have included tables that summarize the commercial organizations selling solid-state and KrF lasers, and a brief summary of organizations actively engaged in R and D on these technologies.

  18. Present status of nuclear fusion research and development in JAERI. 1984 ed.

    International Nuclear Information System (INIS)

    1984-01-01

    This year is the 10th year in the ''Second stage nuclear fusion research and development project'', and the main plan to construct a critical plasma testing apparatus, JT-60, is about to be completed. The test of the power source and control system, and the assembling of the main body were finished, and the final general test is about to be started. In foreign countries, already experiment was begun with the TFTR and the JET, and the formation of the plasma at 20 million deg with the containment time of about 0.3 sec was accomplished. The results of heating experiment by incorporating heating devices are anxiously waited for. As the next generation projects, the conceptual design of the burning core experiment aiming at the attainment of self ignition condition was started in USA, and the next European torus is to be developed in EC before reaching the prototype DEMO. In Japan, it is intended to advanced to the attainment of self ignition condition and an experimental reactor for verifying nuclear fusion technology. In USSR, the construction of a superconducting tokamak T-15 is likely to be completed in 1986. The international cooperation is expected because of the financial condition of respective countries. (Kako, I.)

  19. Compendium of computer codes for the researcher in magnetic fusion energy

    International Nuclear Information System (INIS)

    Porter, G.D.

    1989-01-01

    This is a compendium of computer codes, which are available to the fusion researcher. It is intended to be a document that permits a quick evaluation of the tools available to the experimenter who wants to both analyze his data, and compare the results of his analysis with the predictions of available theories. This document will be updated frequently to maintain its usefulness. I would appreciate receiving further information about codes not included here from anyone who has used them. The information required includes a brief description of the code (including any special features), a bibliography of the documentation available for the code and/or the underlying physics, a list of people to contact for help in running the code, instructions on how to access the code, and a description of the output from the code. Wherever possible, the code contacts should include people from each of the fusion facilities so that the novice can talk to someone ''down the hall'' when he first tries to use a code. I would also appreciate any comments about possible additions and improvements in the index. I encourage any additional criticism of this document. 137 refs

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

    International Nuclear Information System (INIS)

    1987-12-01

    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

  1. Development of a Cost-Effective Design for the Fusion Ignition Research Experiment

    International Nuclear Information System (INIS)

    Philip J. Heitzenroeder

    1999-01-01

    The Fusion Ignition Research Experiment (FIRE) is one of the components of a US Next Step Options (NSO) study which is considering what major experiments might be undertaken in a restructured US Fusion Sciences Program. FIRE is designed for a plasma current of ∼6.5 MA, a burn time of at least 10 s, and a Q in the range of 5 to 10. FIRE has a major radius of 2.0 m, a minor radius of 0.525 m, and a field on axis of 10T. All of the coils are inertially cooled by liquid nitrogen. FIRE will operate primarily in a double null configuration with an x-point triangularity of 0.8 and an x-point elongation of 2.2. In addition to these technical requirements, a major goal for the FIRE project is for a total project cost of approximately $1B (in FY 99 dollars). This paper describes the process and rationale for the engineering design chosen for FIRE, taking into account both the performance and cost goals

  2. 2001 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory

    International Nuclear Information System (INIS)

    Ludwig, Gerson Otto

    2002-01-01

    The year 2001 activities of the controlled thermonuclear fusion research line of the Plasma Associated Laboratory at the National Institute for Space Research - Brazil are reported. The report approaches the staff, participation in congresses, goals for the year 2002 and papers on Tokamak plasmas, plasma diagnostic, bootstraps, plasma equilibrium and diagnostic

  3. Outline of Summary Meeting on Nuclear Fusion Research by Grant-in-Aid (1986-1989) by Monbusho

    International Nuclear Information System (INIS)

    Ishino, Shiori; Nakazawa, Masaharu; Iguchi, Tetsuo

    1990-01-01

    The Summary Meeting on Nuclear Fusion Research by Grant-in-Aid (1986∼1989) of Monbusho was held on Jan. 30∼Feb. 1, 1989 at Gakushi-kaikan in Tokyo. About 300 papers were presented on the research activities as well as some special topics. (author)

  4. An archival study on the nuclear fusion research in Japan later half of 1980's. An interview with SEKIGUCHI Tadashi, Professor Emeritus at the University of Tokyo

    International Nuclear Information System (INIS)

    Nisio, Sigeko; Uematsu, Eisui; Obayashi, Haruo

    2003-05-01

    An interview record with SEKIGUCHI Tadashi, Professor Emeritus at The University of Tokyo, on the nuclear fusion researches in Japan later half of 1980's is given. The major topics concerned are: activities of Science Council of Japan, the establishment of the Japan Society of Plasma Science and Nuclear Fusion Research, the history of establishing National Institute for Fusion Science, and effects of Grant-in-Aid for Scientific Research, and others. (author)

  5. Annual report of the Fusion Research and Development Center for the period of April 1, 1981 to March 31, 1982

    International Nuclear Information System (INIS)

    1982-11-01

    Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1981 to March 1982 are described. Emphasis in the JFT-2 and Doublet III Tokamak programs was placed on high-power heating experiments. JFT-2M, which is to replace JFT-2, is in fabrication and will be operational in early 1983. Construction of JT-60 progressed as planned with its completion targeted in March 1985. In fusion technology programs development of the prototype NBI unit and klystrons for JT-60 made satisfactory progress; particularly rewarding was the demonstration of full capability of the NBI prototype unit in March 1982. The Japanese coil for the IEA Large Coil Task was completed and passed the cooldown test in the domestic test facility. Activities in the design of the near-term FER and INTOR and the power reactor were continued. (author)

  6. Laser fusion

    International Nuclear Information System (INIS)

    Ashby, D.E.T.F.

    1976-01-01

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

  7. Theoretical and simulation research of hydrodynamic instabilities in inertial-confinement fusion implosions

    Science.gov (United States)

    Wang, LiFeng; Ye, WenHua; He, XianTu; Wu, JunFeng; Fan, ZhengFeng; Xue, Chuang; Guo, HongYu; Miao, WenYong; Yuan, YongTeng; Dong, JiaQin; Jia, Guo; Zhang, Jing; Li, YingJun; Liu, Jie; Wang, Min; Ding, YongKun; Zhang, WeiYan

    2017-05-01

    Inertial fusion energy (IFE) has been considered a promising, nearly inexhaustible source of sustainable carbon-free power for the world's energy future. It has long been recognized that the control of hydrodynamic instabilities is of critical importance for ignition and high-gain in the inertial-confinement fusion (ICF) hot-spot ignition scheme. In this mini-review, we summarize the progress of theoretical and simulation research of hydrodynamic instabilities in the ICF central hot-spot implosion in our group over the past decade. In order to obtain sufficient understanding of the growth of hydrodynamic instabilities in ICF, we first decompose the problem into different stages according to the implosion physics processes. The decomposed essential physics pro- cesses that are associated with ICF implosions, such as Rayleigh-Taylor instability (RTI), Richtmyer-Meshkov instability (RMI), Kelvin-Helmholtz instability (KHI), convergent geometry effects, as well as perturbation feed-through are reviewed. Analyti- cal models in planar, cylindrical, and spherical geometries have been established to study different physical aspects, including density-gradient, interface-coupling, geometry, and convergent effects. The influence of ablation in the presence of preheating on the RTI has been extensively studied by numerical simulations. The KHI considering the ablation effect has been discussed in detail for the first time. A series of single-mode ablative RTI experiments has been performed on the Shenguang-II laser facility. The theoretical and simulation research provides us the physical insights of linear and weakly nonlinear growths, and nonlinear evolutions of the hydrodynamic instabilities in ICF implosions, which has directly supported the research of ICF ignition target design. The ICF hot-spot ignition implosion design that uses several controlling features, based on our current understanding of hydrodynamic instabilities, to address shell implosion stability, has

  8. Recent progress of NSTX lithium program and opportunities for magnetic fusion research

    Energy Technology Data Exchange (ETDEWEB)

    Ono, M., E-mail: mono@pppl.gov [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Bell, M.G.; Kaita, R.; Kugel, H.W. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Ahn, J.-W. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Allain, J.P.; Battaglia, D. [Purdue University, West Lafayette, IN 47907 (United States); Bell, R.E. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Canik, J.M. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Ding, S. [Academy of Science Institute of Plasma Physics, Hefei (China); Gerhardt, S. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Gray, T.K. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Guttenfelder, W.; Hosea, J.; Jaworski, M.A.; Kallman, J.; Kaye, S.; LeBlanc, B.P. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); Maingi, R. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States); Mansfield, D.K. [Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543 (United States); and others

    2012-10-15

    Highlights: Black-Right-Pointing-Pointer In this paper, we review the recent progress on the NSTX lithium research. Black-Right-Pointing-Pointer We summarize positive features of lithium effects on plasma. Black-Right-Pointing-Pointer We also point out unresolved issues and unanswered questions on the lithium research. Black-Right-Pointing-Pointer We describe a possible closed liquid lithium divertor tray concept. Black-Right-Pointing-Pointer We note opportunities and challenges of lithium applications for magnetic fusion. - Abstract: Lithium wall coating techniques have been experimentally explored on National Spherical Torus Experiment (NSTX) for the last six 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 dual lithium evaporation system which can evaporate up to {approx}160 g of lithium onto the lower divertor plates between re-loadings. The unique feature of the NSTX lithium research program is that it can investigate the effects of lithium coated plasma-facing components in H-mode divertor plasmas. This lithium evaporation system has produced many intriguing and potentially important results. In 2010, the NSTX lithium program has focused on the effects of liquid lithium divertor (LLD) surfaces including the divertor heat load, deuterium pumping, impurity control, electron thermal confinement, H-mode pedestal physics, and enhanced plasma performance. To fill the LLD with lithium, 1300 g of lithium was evaporated into the NSTX vacuum vessel during the 2010 operations. The routine use of lithium in 2010 has significantly improved the plasma shot availability resulting in a record number of plasma shots in any given year. In this paper, as a follow-on paper from the 1st lithium symposium [1], we review the recent progress toward developing fundamental understanding of the NSTX lithium experimental observations as well as the opportunities and associated R and D required

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  10. Atomic data for heavy element impurities in fusion reactors. Summary report of the final research coordination meeting

    International Nuclear Information System (INIS)

    Clark, R.E.H.

    2009-04-01

    Eleven experts on the properties of heavy elements of relevance to fusion energy research attended the final Research Coordination Meeting (RCM) on Data for Heavy Element Impurities in Fusion Reactors, held at IAEA Headquarters on 4-6 March 2009. Participants summarized their accomplishments with respect to the revised work plan formulated at the second RCM. The overall work plan for the CRP was assessed and reviewed in detail, and achievements were noted. Discussions, conclusions and recommendations of the RCM are briefly described in this report. (author)

  11. Application of neural networks and its prospect. 1. General comment on application to nuclear fusion and plasma researches

    International Nuclear Information System (INIS)

    Takeda, Tatsuoki

    2006-01-01

    The back ground of application of neutral networks to R and D of scientific field and increasing of application fields are stated. A definition of neural networks, the kinds of neural networks and functions, error back propagation, and generalization are explained. An application of multi-layer neural networks to nuclear fusion and plasma researches are described by inverse problem, interpolation, time series prediction, and computerized tomography. Some examples of researches such as MHD of plasma from magnetic probe data of fusion reactor systems, parameter prediction of distribution of the impurity spectra and the charge exchange neutral particle energy spectra, disruption prediction, and residual minimization training neural network are commented. (S.Y.)

  12. Characterization of Size, Composition and Origins of Dust in Fusion Devices. Summary Report of the Third Research Coordination Meeting

    International Nuclear Information System (INIS)

    Braams, B.J.

    2013-02-01

    Twelve experts on processes of dust in fusion experiments met at IAEA Headquarters 30 November - 02 December 2011 for the 3rd Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on ''Characterization of size, composition and origins of dust in fusion devices.'' Participants reviewed their work done in the course of the CRP and the current state of knowledge, and they made plans for a dust database and a final CRP report. Presentations, discussions and recommendations of the RCM are summarized here. (author)

  13. Peaceful fusion

    Energy Technology Data Exchange (ETDEWEB)

    Englert, Matthias [IANUS, TU Darmstadt (Germany)

    2014-07-01

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

  14. Nuclear fusion systems analysis research. FY 1975 annual report, 1 July 1974--30 June 1975

    Energy Technology Data Exchange (ETDEWEB)

    Weatherwax, R.K. (ed.)

    1975-12-31

    This report summarizes research conducted during FY 1975 on the parametric systems analysis of fusion central power stations. As described in the report the methodology being pursued provides for a phased analysis starting with simple ''nominal'' parameters and associated computer codes and progressing to more complex functional models and then to physically based mathematical models for the systems of major significance in future power station viability. The nominal parameter analysis for preliminary screening only derives from consideration of extant reactor point designs and defines a nominal 5000 MWt reactor with either a 900 or 1250 K peak blanket coolant temperature. Functionalized performance and cost models are described for helium Brayton cycle, steam Rankine cycle and binary cycle electric power generation systems.

  15. Safety Culture and Best Practices at Japan's Fusion Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Rule, Keith [PPPL

    2014-05-01

    The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

  16. Nuclear fusion systems analysis research. FY 1975 annual report, 1 July 1974--30 June 1975

    International Nuclear Information System (INIS)

    Weatherwax, R.K.

    1975-01-01

    This report summarizes research conducted during FY 1975 on the parametric systems analysis of fusion central power stations. As described in the report the methodology being pursued provides for a phased analysis starting with simple ''nominal'' parameters and associated computer codes and progressing to more complex functional models and then to physically based mathematical models for the systems of major significance in future power station viability. The nominal parameter analysis for preliminary screening only derives from consideration of extant reactor point designs and defines a nominal 5000 MWt reactor with either a 900 or 1250 K peak blanket coolant temperature. Functionalized performance and cost models are described for helium Brayton cycle, steam Rankine cycle and binary cycle electric power generation systems

  17. Charging large capacitor banks for fusion research using HVDC conversion equipment

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  18. Thermonuclear fusion

    International Nuclear Information System (INIS)

    Weisse, J.

    2000-01-01

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

  19. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  20. Fusion systems engineering

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Summaries of research are included for each of the following topics: (1) fusion reactor systems studies, (2) development of blanket processing technology for fusion reactors, (3) safety studies of fusion concepts, (4) the MACK/MACKLIB system for nuclear response functions, and (5) energy storage and power supply systems for fusion reactors

  1. Report of the second joint Research Committee for Fusion Reactor and Materials. July 12, 2002, Tokyo, Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    Joint research committees in purpose of the discussion on DEMO blanket in view point of the both of reactor technology and materials were held by the Research Committee for Fusion Reactor and Fusion Materials. The joint research committee was held in Tokyo on July 12, 2002. In the committee, the present status of development of solid and liquid breeding blanket, the present status of development of reduced activation structure materials, and IFMIF (International Fusion Materials Irradiation Facility) program were discussed based on the discussions of the development programs of the blanket and materials at the first joint research committee. As a result, it was confirmed that high electric efficiency with 41% would be obtained in the solid breeding blanket system, that neutron radiation data of reduced activation ferritic steel was obtained by HFIR collaboration, and that KEP (key element technology phase) of IFMIF would be finished at the end of 2002 and the data base for the next step, i.e. EVEDA (engineering validation/engineering design activity) was obtained. In addition, the present status of ITER CTA, which was a transient phase for the construction, and the outline of ITER Fast Track, which was an accelerated plan for the performance of the power plants, were reported. This report consists of the summary of the discussion and the viewgraphs which were used at the second joint research committee, and these are very useful for the researchers of the fusion area in Japan. (author)

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

    International Nuclear Information System (INIS)

    2005-06-01

    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

  3. FUSION ENERGY SCIENCES WORKSHOP ON PLASMA MATERIALS INTERACTIONS: Report on Science Challenges and Research Opportunities in Plasma Materials Interactions

    Energy Technology Data Exchange (ETDEWEB)

    Maingi, Rajesh [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Zinkle, Steven J. [University of Tennessee – Knoxville; Foster, Mark S. [U.S. Department of Energy

    2015-05-01

    The realization of controlled thermonuclear fusion as an energy source would transform society, providing a nearly limitless energy source with renewable fuel. Under the auspices of the U.S. Department of Energy, the Fusion Energy Sciences (FES) program management recently launched a series of technical workshops to “seek community engagement and input for future program planning activities” in the targeted areas of (1) Integrated Simulation for Magnetic Fusion Energy Sciences, (2) Control of Transients, (3) Plasma Science Frontiers, and (4) Plasma-Materials Interactions aka Plasma-Materials Interface (PMI). Over the past decade, a number of strategic planning activities1-6 have highlighted PMI and plasma facing components as a major knowledge gap, which should be a priority for fusion research towards ITER and future demonstration fusion energy systems. There is a strong international consensus that new PMI solutions are required in order for fusion to advance beyond ITER. The goal of the 2015 PMI community workshop was to review recent innovations and improvements in understanding the challenging PMI issues, identify high-priority scientific challenges in PMI, and to discuss potential options to address those challenges. The community response to the PMI research assessment was enthusiastic, with over 80 participants involved in the open workshop held at Princeton Plasma Physics Laboratory on May 4-7, 2015. The workshop provided a useful forum for the scientific community to review progress in scientific understanding achieved during the past decade, and to openly discuss high-priority unresolved research questions. One of the key outcomes of the workshop was a focused set of community-initiated Priority Research Directions (PRDs) for PMI. Five PRDs were identified, labeled A-E, which represent community consensus on the most urgent near-term PMI scientific issues. For each PRD, an assessment was made of the scientific challenges, as well as a set of actions

  4. 1st IAEA research co-ordination meeting on charge exchange cross section data for fusion plasma studies. Summary report

    International Nuclear Information System (INIS)

    Janev, R.K.

    1999-02-01

    A brief description of the proceedings and the conclusions of the 1st Research Coordination Meeting on 'Charge Exchange Cross Section Data for Fusion Plasma Studies', held on September 24-25, 1999, at the IAEA Headquarters in Vienna, Austria, is provided. The conclusions of the Meeting regarding the data collection, assessment and generation priorities are also included in the report. (author)

  5. 2003 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory

    International Nuclear Information System (INIS)

    Ludwig, Gerson Otto

    2004-01-01

    This document represents the 2003 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory - Brazil, approaching the areas of toroidal systems for magnetic confinement, plasma heating, current generation and high temperature plasma diagnostic

  6. Fusion systems engineering

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Research during this report period has covered the following areas: (1) fusion reactor systems studies, (2) development of blanket processing technology for fusion reactors, (3) safety studies of fusion concepts, (4) MACKLIB-IV, a new library of nuclear response functions, (5) energy storage and power supply requirements for commercial fusion reactors, (6) blanket/shield design evaluation for commercial fusion reactors, and (7) cross section measurements, evaluations, and techniques

  7. Fusion fuel and renewables

    International Nuclear Information System (INIS)

    Entler, Slavomir

    2015-01-01

    It is shown that fusion fuel meets all aspects applied when defining renewables. A table of definitions of renewables is presented. The sections of the paper are as follows: An industrial renewable source; Nuclear fusion; Current situation in research; Definitions of renewable sources; Energy concept of nuclear fusion; Fusion fuel; Natural energy flow; Environmental impacts; Fusion fuel assessment; Sustainable power; and Energy mix from renewables. (P.A.)

  8. Joint research centre fusion materials irradiations in HFR: Present status and prospectives

    International Nuclear Information System (INIS)

    Casini, G.; Fenici, P.

    1989-01-01

    First a review is made of the Joint Research Centre experimental activity at HFR-Petten in the frame of the Fusion Technology and Safety Programme. The materials under investigation are: Cr-Ni Austenitic steels (316-L type) and Cr-Mn Austenitic steels (AMCR and FI type) as structural materials and Pb-17Li eutetic as tritium breeding material. The experiments on structural materials comprise: Sample irradiations with post-irradiation tensile tests (FRUST) Sample irradiations under constant load and post-irradiation strain measurement (TRIESTE) On-line creep tests (CRISP). The experiments on Pb-17Li breeder material regard sample irradiations to investigate tritium production and recovery as well as tritium permeation through blanket structures (LIBRETTO Experiment). Both irradiations on structural and breeding materials will be pursued up to the end of the current JRC-Multiannual Programme (1988-1991) and even further. In the last part of the paper expected developments of the testing programme at HFR are discussed. New areas of research should involve materials for divertor applications (NET/ITER) and advanced low activation composite materials for Commercial Power Reactors

  9. Report of the 2nd workshop on particle material interactions for fusion research

    International Nuclear Information System (INIS)

    Ozawa, Kunio; Gesi, Kazuo; Iwata, Tadao

    1984-02-01

    The plenary session of the sub-committee for the data-banking of particle-material interactions in the Research Committee of A M Data Center was held at the JAERI Headquarters, Tokyo, February 24 and 25, 1982. The subsequent local meeting was held in Osaka branch office of JAERI, June 10, 1982. The aim of this workshop has been not only to make clear the present status in the A M data banking and the material science relevant to fusion research, but also to obtain an overview of the approaches that should be developed for solving the problems. In these workshops, 16 papers on the specified fields were presented by the committee members. This report contains these papers, and the investigation report in 1982 fiscal year on Diffusional Behaviour of Hydrogen and it's Isotope in Iron and Steel is added supplementarily. The contents of this report are composed of 4 chapters which are connected with each other concerning A M activities of hydrogen recycling: 1) Perspective review, 2) Re-emission and Retention, 3) Desorption and Diffusion, and 4) Radiation effects of neutron and ions on hydrogen recycling process. (author)

  10. Recent progress in ignition fusion research on the National Ignition Facility

    International Nuclear Information System (INIS)

    Leeper, Ramon J.

    2011-01-01

    This paper will review the ignition fusion research program that is currently being carried out on the National Ignition Facility (NIF) located at Lawrence Livermore National Laboratory. This work is being conducted under the auspices of the National Ignition Campaign (NIC) that is a broad collaboration of national laboratories and universities that together have developed a detailed research plan whose goal is ignition in the laboratory. The paper will begin with a description of the NIF facility and associated experimental facilities. The paper will then focus on the ignition target and hohlraum designs that will be tested in the first ignition attempts on NIF. The next topic to be introduced will be a description of the diagnostic suite that has been developed for the initial ignition experiments on NIF. The paper will then describe the experimental results that were obtained in experiments conducted during the fall of 2009 on NIF. Finally, the paper will end with a description of the detailed experimental plans that have been developed for the first ignition campaign that will begin later this year. (author)

  11. JSPS-CAS Core University Program seminar on summary of 10-year collaborations in plasma and nuclear fusion research area

    International Nuclear Information System (INIS)

    Toi, Kazuo; Wang Kongjia

    2011-07-01

    The JSPS-CAS Core University Program (CUP) seminar on “Summary of 10-year Collaborations in Plasma and Nuclear Fusion Research Area” was held from March 9 to March 11, 2011 in the Okinawa Prefectural Art Museum, Naha city, Okinawa, Japan. The collaboration program on plasma and nuclear fusion started from 2001 under the auspices of Japanese Society of Promotion of Science (JSPS) and Chinese Academy of Sciences (CAS). This year is the last year of the CUP. This seminar was organized in the framework of the CUP. In the seminar, 29 oral talks were presented, having 14 Chinese and 30 Japanese participants. These presentations covered key topics related to the collaboration categories: (1) improvement of core plasma properties, (2) basic research on fusion reactor technologies, and (3) theory and numerical simulation. This seminar aims at summarizing the results obtained through the collaborations for 10 years, and discussing future prospects of China-Japan collaboration in plasma and nuclear fusion research areas. (author)

  12. Light-ion inertial confinement fusion research at Naval Research Laboratory

    International Nuclear Information System (INIS)

    Cooperstein, G.; Colombant, D.G.; Barker, R.J.

    1983-01-01

    High-brightness proton beams (0.4 MA, 1 MV) have recently been extracted from 20 cm 2 axial pinch-reflex diodes (PRDs) mounted on the NRL Gamble II generator. A source power brightness of >=10 TW.cm - 2 .rad - 2 was achieved in these experiments. A new barrel-shaped equatorial PRD that can be coupled to PBFA II has also been operated on Gamble II and has demonstrated 50% proton efficiency with predominantly azimuthally symmetric charged-particle flow. In other experiments the stopping power of deuterons in hot plasmas was measured using a PRD on Gamble II. Results show about 40% increase in stopping power over that in cold targets when the beam was focused to about 0.25 MA.cm - 2 . Research is also being performed on transporting ion beams in large-diameter channels (>or approx. 2.5 cm) and on a post-transport plasma-filled magnetic focusing section to bring the beam to pellet dimensions. (author)

  13. Establishment of KAERI Strategy and Organization for Fusion Power Technology Research

    International Nuclear Information System (INIS)

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

    2005-04-01

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

  14. Investigations of Materials under High Repetition and Intense Fusion Pulses. Report of a Coordinated Research Project 2011-2016

    International Nuclear Information System (INIS)

    2017-12-01

    This publication presents experimental simulations of plasma-surface interaction phenomena at extreme conditions as expected in a fusion reactor, using dedicated test bed devices such as dense plasma focus, particle accelerators, plasma accelerators and plasma guns. It includes the investigation of the mechanism of material damage during transient heat loads on materials and addresses, in particular, the performance and adequacy of tungsten as plasma facing material for the next step fusion devices, such as ITER and fusion demonstration power plants. The publication is a compilation of the main results and findings of an IAEA coordinated research project on investigations on materials under high repetition and intense fusion pulses, conducted in the period 2011-2016 and provides a practical knowledge base for scientists and engineers carrying out activities in the plasma-material surface interaction area. Through its coordinated research activities, the IAEA has made it possible for States that are not yet members of the ITER project to contribute to ITER relevant scientific investigations, which have led to increased capabilities of diagnostics for plasma surface interaction.

  15. Summary of the 16th IAEA Technical Meeting on 'Research using Small Fusion Devices'

    International Nuclear Information System (INIS)

    Gribkov, V.; Oost, G. van; Malaquias, A.; Herrera, J.

    2006-01-01

    Common research topics that are being studied in small, medium and large devices such as H-mode like or improved confinement, turbulence and transport are reported. These included modelling and diagnostic developments for edge and core, to characterize plasma density, temperature, electric potential, plasma flows, turbulence scale, etc. Innovative diagnostic methods were designed and implemented which could be used to develop experiments in small devices (in some cases not possible in large devices due to higher power deposition) to allow a better understanding of plasma edge and core properties. Reports are given addressing research in linear devices that can be used to study particular plasma physics topics relevant for other magnetic confinement devices such as the radial transport and the modelling of self-organized plasma jets involved in spheromak-like plasma formation. Some aspects of the work presented are of interest to the astrophysics community since they are believed to shed light on the basis of the physics of stellar jets. On the dense magnetized plasmas (DMP) topic, the present status of research, operation of new devices, plasma dynamics modelling and diagnostic developments is reported. The main devices presented belong to the class of Z-pinches, mostly plasma foci, and several papers were presented under this topic. The physics of DMP is important both for the main-stream fusion investigations as well as for providing the basis for elaboration of new concepts. New high-current technology introduced in the DMP devices design and construction make these devices nowadays more reliably fitted to various applications and give the possibility to widen the energy range used by them in both directions-to the multi-MJ level facilities and down to miniature plasma focus devices with energy of just a few J. (conference report)

  16. Program for development of high-field superconducting magnets for fusion research

    International Nuclear Information System (INIS)

    1975-01-01

    Three superconducting magnet programs at LLL are outlined. The first program, the one considered in greatest detail, is a developmental program in which LLL will work closely with superconductor manufacturers to develop multifilamentary Nb 3 Sn superconductor suitable for use in large CTR magnets. The result of this program will be the fabrication of a rather large magnet (but one that is much smaller than future CTR magnets) and the determination of its performance limitations. In the second program, the developed multifilamentary Nb 3 Sn superconductor will be used to construct the magnets for the Fusion Engineering Research Facility (FERF) machine. In this program, the bulk of the effort will be in magnet design and winding. The third program chronologically overlaps the first two programs. This program includes the fabrication and testing of the superconducting magnets for the MX machine although, as explained in the Technical Plan, only the cost of the development work is included in this document. At the present time, Nb--Ti superconductor is being considered. Apart from some initial conductor design work, the major effort will be in magnet design and winding

  17. Performance of a 200-J KrF laser amplifier for laser fusion research

    International Nuclear Information System (INIS)

    Owadano, Y.; Okuda, I.; Tanimoto, M.; Kasai, T.; Matsumoto, Y.; Yaoita, A.; Nemoto, F.; Komeiji, S.; Yano, M.

    1986-01-01

    An e-beam-pumped KrF laser has been developed as a middle-stage amplifier of a 1-kJ system for laser fusion research. The laser consists of one Marx generator (1MV, 11kJ), two PFLs (4.6 Ω, 100ns) with laser triggered output switches, two e-beam diodes (10 X 60 cm/sup 2/), and a laser cell (20- X 20- X 60-cm/sup 3/ active volume). Two e-beams are injected into the cell through carbon-sprayed Kapton anode and pressure foils. Up to now, a 120-J (70-ns) laser pulse has been generated with a 90% output coupling flat-flat resonator at 80% voltage operation. Overall efficiency is 1.5% in this case. A series of experiments has been performed with the laser to measure gain characteristics of a Kr-rich mixture, which is predicted to be more efficient than a normal Ar mixture in a high-laser-intensity region (>10 MW cm/sup -2/). An injection-locked oscillator mode was used to obtain a well-defined high-intensity laser beam, and a saturated intracavity intensity was measured

  18. The Fusion Science Research Plan for the Major U.S. Tokamaks. Advisory report

    International Nuclear Information System (INIS)

    1996-01-01

    In summary, the community has developed a research plan for the major tokamak facilities that will produce impressive scientific benefits over the next two years. The plan is well aligned with the new mission and goals of the restructured fusion energy sciences program recommended by FEAC. Budget increases for all three facilities will allow their programs to move forward in FY 1997, increasing their rate of scientific progress. With a shutdown deadline now established, the TFTR will forego all but a few critical upgrades and maximize operation to achieve a set of high-priority scientific objectives with deuterium-tritium plasmas. The DIII-D and Alcator C-Mod facilities will still fall well short of full utilization. Increasing the run time in vii DIII-D is recommended to increase the scientific output using its existing capabilities, even if scheduled upgrades must be further delayed. An increase in the Alcator C-Mod budget is recommended, at the expense of equal and modest reductions (~1%) in the other two facilities if necessary, to develop its capabilities for the long-term and increase its near-term scientific output.

  19. Study of neoclassical transport in the 1/ν regime for a research fusion reactor

    International Nuclear Information System (INIS)

    Kalyuzhnyj, V.N.; Kasilov, S.V.; Nemov, V.V.

    2005-01-01

    In frame of the concept of a steady-state operated research fusion reactor (RFR) in papers [1-4] the RFR with an increased plasma-wall detachment was proposed with the purpose to enable not only the production but also a long-term confinement of a self-sustained plasma at the existing technology level. In connection with complication of the corresponding magnetic configuration an investigation of the neoclassical transport is desirable for such systems. In the present work neoclassical transport for a magnetic configuration of l=2 torsatron type variant of RFR system with an additional opposite toroidal magnetic field is investigated numerically. A so-called 1/ν transport regime, in which the transport coefficients are increased with reduction of particle collision frequency ν is considered. For calculating of transport coefficients a technique, based on integration along magnetic field lines in a given stellarator magnetic field is used. The magnetic field of helical windings is calculated by Biot-Savart law. The obtained transport coefficients are presented in a standard form containing a factor depending on the magnetic field geometry. From analysis of the received results follows that in respect of the neoclassical transport the proposed magnetic configuration turns out to be closer to configuration of the classical stellarator (with helical winding), than to configuration of the classical torsatron/geliotron. (author)

  20. Towards a new generation of control and data acquisition systems for thermonuclear fusion research

    International Nuclear Information System (INIS)

    Van Haren, P.C.

    1993-01-01

    Because of the complexity of thermonuclear fusion test reactors, control systems are indispensable. The physical properties of the reactor medium, i.e. the plasma, are still not well understood. Therefore, many diagnostic techniques are applied to investigate the plasma and to discover its properties. As a consequence, data acquisition systems play an important role in thermonuclear fusion research. This thesis reports on three projects that were carried out in the field of control and data acquisition. The target experiment is the Rijnhuizen Tokamak Project (RTP), a medium-sized experiment dedicated to studies of transport in the reactor medium. One of the projects is aimed at the development of a new Plasma Position and Current Control feedback System (PPCCS). This system evaluates signals of a large (about 20) number of sensors, computes the actual state of the plasma from these signals and generates command signals for the power supplies that govern the plasma position. The most ambitious project described in this thesis is the development of a data acquisition system, called TRAMP (Transient Recorders and Amoeba Multi Processor), that aims to be a testbed for smart data acquisition strategies. TRAMP attempts to acquire and store temporarily all possible data at a high sampling frequency from a single RTP pulse, and accommodates for a resampling in software prior to transferring the data to a mass storage facility. The software resampling frequency can be tuned by analysis of the acquired data and, in that way, only interesting data will be stored. In the course of the development of both the above-mentioned systems it turned out that the existing database format applied for managing experimental data provided many hurdles in the realization of efficient solutions. Consequently, a new database format was developed together with software to deal with it. This new database, called DOM4 (Data Organization and Management), is now applied at all data acquisition

  1. Assessment of some of the problems in the USA of superconducting magnets for fusion research

    International Nuclear Information System (INIS)

    Cornish, D.N.

    1981-01-01

    This paper discusses some of the general difficulties and problems encountered during the development of the technology of superconductors and superconducting magnets for fusion and expresses some personal concerns

  2. Research on Methods of Infrared and Color Image Fusion Based on Wavelet Transform

    Directory of Open Access Journals (Sweden)

    Zhao Rentao

    2014-06-01

    Full Text Available There is significant difference in the imaging features of infrared image and color image, but their fusion images also have very good complementary information. In this paper, based on the characteristics of infrared image and color image, first of all, wavelet transform is applied to the luminance component of the infrared image and color image. In multi resolution the relevant regional variance is regarded as the activity measure, relevant regional variance ratio as the matching measure, and the fusion image is enhanced in the process of integration, thus getting the fused images by final synthesis module and multi-resolution inverse transform. The experimental results show that the fusion image obtained by the method proposed in this paper is better than the other methods in keeping the useful information of the original infrared image and the color information of the original color image. In addition, the fusion image has stronger adaptability and better visual effect.

  3. Progress report on research and development work 1983 of the nuclear fusion project

    International Nuclear Information System (INIS)

    Finken, D.

    1984-02-01

    The studies of the Kernforschungszentrum Karlsruhe on fusion using magnetic confinement are included in the nuclear fusion project and embedded into the European Fusion Technology Programme. The studies are promoted via an association contract between KfK and Euratom by the European Commission. Some of the studies exceed the volume defined in the technology programme. These contributions, most of them studies, help to connect the various sectors and prepare new tasks, with regard to the extension of the technology programme to be expected in the coming years and the planning activities for NET. The reports summarized here are contributions of the institutes and thus arranged according to organization units. The tasks which the KfK has taken over from the Fusion Technology Programme of the EC are compiled in the appendix. (orig./GG) [de

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

    International Nuclear Information System (INIS)

    PROJECT STAFF

    2003-01-01

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

  5. Fusion Canada issue 23

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-01

    A short bulletin from the National Fusion Program highlighting in this issue TdeV tokamak updates, fusion research in Korea, CCFM program review, TdeV divertor plasma, and CFFTP program review. 4 figs.

  6. Fusion Canada issue 20

    International Nuclear Information System (INIS)

    1993-03-01

    Fusion Canada's publication of the National Fusion Program. Included in this issue is the CFFTP Industrial Impact Study, CCFM/TdeV Update:helium pumping, research funds, and deuterium in beryllium - high temperature behaviour. 3 figs

  7. Fusion Canada issue 23

    International Nuclear Information System (INIS)

    1994-01-01

    A short bulletin from the National Fusion Program highlighting in this issue TdeV tokamak updates, fusion research in Korea, CCFM program review, TdeV divertor plasma, and CFFTP program review. 4 figs

  8. Fusion Canada issue 6

    International Nuclear Information System (INIS)

    1989-02-01

    A short bulletin from the National Fusion Program. Included in this issue is a funding report for CFFTP, a technical update for Tokamak de Varennes and a network for university research by the National Fusion Program. 4 figs

  9. Neutron transport-burnup code MCORGS and its application in fusion fission hybrid blanket conceptual research

    Science.gov (United States)

    Shi, Xue-Ming; Peng, Xian-Jue

    2016-09-01

    Fusion science and technology has made progress in the last decades. However, commercialization of fusion reactors still faces challenges relating to higher fusion energy gain, irradiation-resistant material, and tritium self-sufficiency. Fusion Fission Hybrid Reactors (FFHR) can be introduced to accelerate the early application of fusion energy. Traditionally, FFHRs have been classified as either breeders or transmuters. Both need partition of plutonium from spent fuel, which will pose nuclear proliferation risks. A conceptual design of a Fusion Fission Hybrid Reactor for Energy (FFHR-E), which can make full use of natural uranium with lower nuclear proliferation risk, is presented. The fusion core parameters are similar to those of the International Thermonuclear Experimental Reactor. An alloy of natural uranium and zirconium is adopted in the fission blanket, which is cooled by light water. In order to model blanket burnup problems, a linkage code MCORGS, which couples MCNP4B and ORIGEN-S, is developed and validated through several typical benchmarks. The average blanket energy Multiplication and Tritium Breeding Ratio can be maintained at 10 and 1.15 respectively over tens of years of continuous irradiation. If simple reprocessing without separation of plutonium from uranium is adopted every few years, FFHR-E can achieve better neutronic performance. MCORGS has also been used to analyze the ultra-deep burnup model of Laser Inertial Confinement Fusion Fission Energy (LIFE) from LLNL, and a new blanket design that uses Pb instead of Be as the neutron multiplier is proposed. In addition, MCORGS has been used to simulate the fluid transmuter model of the In-Zinerater from Sandia. A brief comparison of LIFE, In-Zinerater, and FFHR-E will be given.

  10. Frontiers in propulsion research: Laser, matter-antimatter, excited helium, energy exchange thermonuclear fusion

    Science.gov (United States)

    Papailiou, D. D. (Editor)

    1975-01-01

    Concepts are described that presently appear to have the potential for propulsion applications in the post-1990 era of space technology. The studies are still in progress, and only the current status of investigation is presented. The topics for possible propulsion application are lasers, nuclear fusion, matter-antimatter annihilation, electronically excited helium, energy exchange through the interaction of various fields, laser propagation, and thermonuclear fusion technology.

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

    International Nuclear Information System (INIS)

    1976-07-01

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

  12. Nuclear fusion

    International Nuclear Information System (INIS)

    Al-zaelic, M.M.

    2013-01-01

    Nuclear fusion can be relied on to solve the global energy crisis if the process of limiting the heat produced by the fusion reaction (Plasma) is successful. Currently scientists are progressively working on this aspect whereas there are two methods to limit the heat produced by fusion reaction, the two methods are auto-restriction using laser beam and magnetic restriction through the use of magnetic fields and research is carried out to improve these two methods. It is expected that at the end of this century the nuclear fusion energy will play a vital role in overcoming the global energy crisis and for these reasons, acquiring energy through the use of nuclear fusion reactors is one of the most urge nt demands of all mankind at this time. The conclusion given is that the source of fuel for energy production is readily available and inexpensive ( hydrogen atoms) and whole process is free of risks and hazards, especially to general health and the environment . Nuclear fusion importance lies in the fact that energy produced by the process is estimated to be about four to five times the energy produced by nuclear fission. (author)

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

    International Nuclear Information System (INIS)

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

    2013-09-01

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

  14. Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL 3.0). Summary report of the Third Research Coordination Meeting

    International Nuclear Information System (INIS)

    Sawan, Mohamed E.

    2012-03-01

    The third Research Co-ordination Meeting of the Nuclear Data Libraries for Advanced Systems - Fusion Devices (FENDL-3) was held at IAEA Headquarters in Vienna from 6 to 9 December 2011. A summary of the presentations given during meeting is given in this report along with the discussions that took place. A list of actions necessary to complete the library production, processing and testing are given. Details of the documents arising from the CRP were agreed. (author)

  15. Research on the Fusion of Dependent Evidence Based on Rank Correlation Coefficient

    Directory of Open Access Journals (Sweden)

    Fengjian Shi

    2017-10-01

    Full Text Available In order to meet the higher accuracy and system reliability requirements, the information fusion for multi-sensor systems is an increasing concern. Dempster–Shafer evidence theory (D–S theory has been investigated for many applications in multi-sensor information fusion due to its flexibility in uncertainty modeling. However, classical evidence theory assumes that the evidence is independent of each other, which is often unrealistic. Ignoring the relationship between the evidence may lead to unreasonable fusion results, and even lead to wrong decisions. This assumption severely prevents D–S evidence theory from practical application and further development. In this paper, an innovative evidence fusion model to deal with dependent evidence based on rank correlation coefficient is proposed. The model first uses rank correlation coefficient to measure the dependence degree between different evidence. Then, total discount coefficient is obtained based on the dependence degree, which also considers the impact of the reliability of evidence. Finally, the discount evidence fusion model is presented. An example is illustrated to show the use and effectiveness of the proposed method.

  16. Research on the Fusion of Dependent Evidence Based on Rank Correlation Coefficient.

    Science.gov (United States)

    Shi, Fengjian; Su, Xiaoyan; Qian, Hong; Yang, Ning; Han, Wenhua

    2017-10-16

    In order to meet the higher accuracy and system reliability requirements, the information fusion for multi-sensor systems is an increasing concern. Dempster-Shafer evidence theory (D-S theory) has been investigated for many applications in multi-sensor information fusion due to its flexibility in uncertainty modeling. However, classical evidence theory assumes that the evidence is independent of each other, which is often unrealistic. Ignoring the relationship between the evidence may lead to unreasonable fusion results, and even lead to wrong decisions. This assumption severely prevents D-S evidence theory from practical application and further development. In this paper, an innovative evidence fusion model to deal with dependent evidence based on rank correlation coefficient is proposed. The model first uses rank correlation coefficient to measure the dependence degree between different evidence. Then, total discount coefficient is obtained based on the dependence degree, which also considers the impact of the reliability of evidence. Finally, the discount evidence fusion model is presented. An example is illustrated to show the use and effectiveness of the proposed method.

  17. Barriers to fusion

    International Nuclear Information System (INIS)

    Berriman, A.C.; Butt, R.D.; Dasgupta, M.; Hinde, D.J.; Morton, C.R.; Newton, J.O.

    1999-01-01

    The fusion barrier is formed by the combination of the repulsive Coulomb and attractive nuclear forces. Recent research at the Australian National University has shown that when heavy nuclei collide, instead of a single fusion barrier, there is a set of fusion barriers. These arise due to intrinsic properties of the interacting nuclei such deformation, rotations and vibrations. Thus the range of barrier energies depends on the properties of both nuclei. The transfer of matter between nuclei, forming a neck, can also affect the fusion process. High precision data have been used to determine fusion barrier distributions for many nuclear reactions, leading to new insights into the fusion process

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

    International Nuclear Information System (INIS)

    Johnson, R.K.; Thomson, H.A.

    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

  19. DIII-D research advancing the scientific basis for burning plasmas and fusion energy

    Science.gov (United States)

    W. M. SolomonThe DIII-D Team

    2017-10-01

    The DIII-D tokamak has addressed key issues to advance the physics basis for ITER and future steady-state fusion devices. In work related to transient control, magnetic probing is used to identify a decrease in ideal stability, providing a basis for active instability sensing. Improved understanding of 3D interactions is emerging, with RMP-ELM suppression correlated with exciting an edge current driven mode. Should rapid plasma termination be necessary, shattered neon pellet injection has been shown to be tunable to adjust radiation and current quench rate. For predictive simulations, reduced transport models such as TGLF have reproduced changes in confinement associated with electron heating. A new wide-pedestal variant of QH-mode has been discovered where increased edge transport is found to allow higher pedestal pressure. New dimensionless scaling experiments suggest an intrinsic torque comparable to the beam-driven torque on ITER. In steady-state-related research, complete ELM suppression has been achieved that is relatively insensitive to q 95, having a weak effect on the pedestal. Both high-q min and hybrid steady-state plasmas have avoided fast ion instabilities and achieved increased performance by control of the fast ion pressure gradient and magnetic shear, and use of external control tools such as ECH. In the boundary, experiments have demonstrated the impact of E× B drifts on divertor detachment and divertor asymmetries. Measurements in helium plasmas have found that the radiation shortfall can be eliminated provided the density near the X-point is used as a constraint in the modeling. Experiments conducted with toroidal rings of tungsten in the divertor have indicated that control of the strike-point flux is important for limiting the core contamination. Future improvements are planned to the facility to advance physics issues related to the boundary, transients and high performance steady-state operation.

  20. Annual report of the Fusion Research Center for the period of April 1, 1983 to March 31, 1984

    International Nuclear Information System (INIS)

    1985-03-01

    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)