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Journal Articles

ITER and plasma surface interaction issues in a fusion reactor

Shimomura, Yasuo

Journal of Nuclear Materials, 363-365, p.467 - 475, 2007/06

 Times Cited Count:29 Percentile:86.52(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Preparation of ITER construction and operation

Shimomura, Yasuo

Fusion Engineering and Design, 81(1-7), p.3 - 11, 2006/02

 Times Cited Count:4 Percentile:30.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ITER towards the construction

Shimomura, Yasuo

Fusion Engineering and Design, 74(1-4), p.9 - 16, 2005/11

 Times Cited Count:21 Percentile:78.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Toward construction of ITER

Shimomura, Yasuo

Purazuma, Kaku Yugo Gakkai-Shi, 81(3), p.143 - 148, 2005/03

The objective of ITER Project is to investigate burning plasmas, to sustain a fusion power of 500 MW for a long period and to demonstrate technologies essential for a power reactor. A steady progress is being made in the technical preparation toward the start of construction on the basis of developments attained during the Engineering Design Activity (EDA), which was completed in 2001. The ITER Negotiators have developed a draft Joint Implementation Agreement (JIA), ready for completion following the nomination of the Director General of the Project(DG). The final high-level negotiations are focused on siting and the concluding details of cost sharing. The EU, with Cadarache, and Japan, with Rokkasho, have both promised large contributions to the project to strongly support their construction site proposals. Large contributions to a broader collaboration among the Parties are also proposed by them. This covers complementary activities to help accelerate fusion development towards a viable power source, and may allow the Participants to reach a conclusion on ITER siting.

Journal Articles

The Present status and future prospects of the ITER project

Shimomura, Yasuo

Journal of Nuclear Materials, 329-333(1), p.5 - 11, 2004/08

 Times Cited Count:22 Percentile:79.05(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Overview of physics basis for ITER

Mukhovatov, V.*; Shimada, Michiya; Chudnovskiy, A. N.*; Costley, A. E.*; Gribov, Y.*; Federici, G.*; Kardaun, O. J. F.*; Kukushkin, A. S.*; Polevoi, A. R.*; Pustovitov, V. D.*; et al.

Plasma Physics and Controlled Fusion, 45(12), p.235 - 252, 2003/12

 Times Cited Count:55 Percentile:83.33(Physics, Fluids & Plasmas)

ITER will be the first magnetic confinement device with burning DT plasma and fusion power of about 0.5 GW. During the past few years, new results have been obtained that substantiate the confidence in achieving Q $$>$$ 10 in ITER with inductive H-mode operation. These include achievement of a good H-mode confinement near the Greenwald density at high triangularity of the plasma cross section; improvements in theory-based confinement projections for the core plasma; improvement in helium ash removal due to the elastic collisions of He atoms with D/T ions in the divertor predicted by modelling; demonstration of feedback control of NTMs and resultant improvement in the achievable beta-values; better understanding of ELM physics and development of ELM mitigation techniques; and demonstration of mitigation of plasma disruptions. ITER will have a flexibility to operate also in steady state and intermediate (hybrid) regimes. The paper concentrates on inductively driven plasma performance and discusses requirements for steady-state operation in ITER.

Journal Articles

Comparison of ITER performance predicted by semi-empirical and theory-based transport models

Mukhovatov, V.*; Shimomura, Yasuo; Polevoi, A. R.*; Shimada, Michiya; Sugihara, Masayoshi; Bateman, G.*; Cordey, J. G.*; Kardaun, O. J. F.*; Pereverzev, G. V.*; Voitsekhovich, I.*; et al.

Nuclear Fusion, 43(9), p.942 - 948, 2003/09

 Times Cited Count:43 Percentile:76.6(Physics, Fluids & Plasmas)

The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different methods are compared. The first method utilises an empirical confinement time scaling and prescribed radial profiles of transport coefficients, the second approach extrapolates from especially designed ITER similarity experiments, and the third approach is based on partly theory-based transport models. The energy confinement time given by the ITERH-98(y,2) scaling for an inductive scenario with plasma current of 15 MA and plasma density 15% below the Greenwald density is 3.7 s with one estimated technical standard deviation of 14%. This translates in the first approach into an interval for Q of [6-15] at the auxiliary heating power Paux = 40 MW and [6-30] at the minimum heating power satisfying a good confinement ELMy H-mode. Predictions of similarity experiments from JET and of theory-based transport models overlap with the prediction using the empirical confinement-time scaling within its estimated margin of uncertainty.

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Overview of International Thermonuclear Experimental Reactor(ITER) engineering design activities

Shimomura, Yasuo

Physics of Plasmas, 1(5, Part2), p.1612 - 1618, 1994/05

no abstracts in English

Journal Articles

Feasibility studies on plasma vertical position control by ex-vessel coils in ITER-like tokamak fusion reactors

Nishio, Satoshi; Sugihara, Masayoshi; Shimomura, Yasuo

Fusion Engineering and Design, 23, p.17 - 31, 1993/00

 Times Cited Count:4 Percentile:44.86(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Comparative study of low and high aspect ratio devices for ITER design options

Sugihara, Masayoshi; Tada, Eisuke; Shimomura, Yasuo; Tsunematsu, Toshihide; Nishio, Satoshi; *; *; Koizumi, Koichi;

JAERI-M 92-136, 43 Pages, 1992/09

JAERI-M-92-136.pdf:1.34MB

no abstracts in English

JAEA Reports

Comparison between a steady-state fusion reactor and an inductively driven pulse reactor

*; Horiike, Hiroshi; Kuroda, Toshimasa*; Matsuzaki, Yoshimi; Shimomura, Yasuo; Sugihara, Masayoshi

JAERI-M 92-056, 53 Pages, 1992/04

JAERI-M-92-056.pdf:1.22MB

no abstracts in English

JAEA Reports

Japanese contribution of ITER PF systems design during CDA

Azumi, Masafumi; Hasegawa, Mitsuru*; *; Kurihara, Kenichi; Nakamura, Yukiharu; Nishio, Satoshi; Shimomura, Yasuo; Shinya, K.*; Sugihara, Masayoshi; *; et al.

JAERI-M 92-041, 100 Pages, 1992/03

JAERI-M-92-041.pdf:2.59MB

no abstracts in English

Journal Articles

Separatrix sweeping by in-vessel coils on a fusion reactor

Nishio, Satoshi; Araki, Masanori; Shinya, K.*; Shimizu, Katsusuke*; Kuroda, Toshimasa*; Sugihara, Masayoshi; Shimomura, Yasuo

Fusion Engineering and Design, 19, p.203 - 211, 1992/00

 Times Cited Count:2 Percentile:27.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study on operational capability of ITER

*; Mizoguchi, Tadanori*; Shimomura, Yasuo; Sugihara, Masayoshi; Tsunematsu, Toshihide

JAERI-M 91-209, 38 Pages, 1991/12

JAERI-M-91-209.pdf:1.25MB

no abstracts in English

Journal Articles

Impact of engineering constraints on fusion reactors

Mizoguchi, Tadanori*; Shimomura, Yasuo

Kaku Yugo Kenkyu, 65(2), p.115 - 141, 1991/02

no abstracts in English

JAEA Reports

Energy confinement scaling based on offset linear characteristic

Odajima, Kazuo; Shimomura, Yasuo

JAERI-M 88-068, 18 Pages, 1988/03

JAERI-M-88-068.pdf:0.45MB

no abstracts in English

JAEA Reports

Japanese contribution to INTOR Workshop,Phase IIA,Part 3; Group B; Operational limits and confinement

Tsunematsu, Toshihide; Azumi, Masafumi; Matsumoto, Hiroshi; *; ; Shimomura, Yasuo; Sugihara, Masayoshi; Suzuki, Norio; Takizuka, Tomonori; Tokuda, Shinji

JAERI-M 88-029, 95 Pages, 1988/02

JAERI-M-88-029.pdf:1.89MB

no abstracts in English

JAEA Reports

Empirical scaling of energy confinement time of L-mode and optimized mode and some consideration of reactor core plasma in tokamak

Shimomura, Yasuo; Suzuki, Norio; Sugihara, Masayoshi; ; Odajima, Kazuo; Tsunematsu, Toshihide

JAERI-M 87-080, 25 Pages, 1987/06

JAERI-M-87-080.pdf:0.47MB

no abstracts in English

Journal Articles

Empirical scaling of incremental energy confinement time of L-mode plasma and comments on improved confinement in tokamaks

;

Comments Plasma Phys.Controll.Fus., 10(05), p.207 - 216, 1987/05

no abstracts in English

70 (Records 1-20 displayed on this page)