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Journal Articles

Performance of ITER as a burning plasma experiment

Shimada, Michiya; Mukhovatov, V.*; Federici, G.*; Gribov, Y.*; Kukushkin, A.*; Murakami, Yoshiki*; Polevoi, A. R.*; Pustovitov, V. D.*; Sengoku, Seio; Sugihara, Masayoshi

Nuclear Fusion, 44(2), p.350 - 356, 2004/02

Recent performance analysis has improved confidence in achieving Q $$>$$ 10 in inductive operation in ITER. Performance analysis based on empirical scaling shows the feasibility of achieving Q $$>$$ 10 in inductive operation with a sufficient margin. Theory-based core modeling indicates the need of high pedestal temperature (2-4 keV) to achieve Q $$>$$ 10, which is in the range of projection with pedestal scaling. The heat load of type-I ELM could be made tolerable by high density operation and further tilting the target plate (if necessary). Pellet injection from High-Field Side would be useful in enhancing Q and reducing ELM heat load. Steady state operation scenarios have been developed with modest requirement on confinement improvement and beta (HH98(y,2) $$>$$ 1.3 and betaN $$>$$ 2.6). Stabilisation of RWM, required in such regimes, is feasible with the present saddle coils and power supplies with double-wall structure taken into account.

Journal Articles

Performance of ITER as a burning plasma experiment

Shimada, Michiya; Mukhovatov, V.*; Federici, G.*; Gribov, Y.*; Kukushkin, A. S.*; Murakami, Yoshiki*; Polevoi, A. R.*; Pustovitov, V. D.*; Sengoku, Seio; Sugihara, Masayoshi

Nuclear Fusion, 44(2), p.350 - 356, 2004/02

 Times Cited Count:39 Percentile:75.72(Physics, Fluids & Plasmas)

Performance analysis based on empirical scaling shows the feasibility of achieving Q $$geq$$ 10 in inductive operation. Analysis has also elucidated a possibility that ITER can potentially demonstrate Q $$sim$$ 50, enabling studies of self-heated plasmas. Theory-based core modeling indicates the need of high pedestal temperature (3.2 - 5.3 keV) to achieve Q $$geq$$10, which is in the range of projection with presently available pedestal scalings. Pellet injection from high-field side would be useful in enhancing Q and reducing ELM heat load in high plasma current operation. If the ELM heat load is not acceptable, it could be made tolerable by further tilting the target plate. Steady state operation scenarios at Q = 5 have been developed with modest requirement on confinement improvement and beta (HH98(y,2) $$geq$$ 1.3 and betaN $$geq$$ 2.6). Stabilisation of RWM, required in such regimes, is feasible with the present saddle coils and power supplies with double-wall structure taken into account.

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Chujo, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

no abstracts in English

JAEA Reports

Transport analysis of tungsten impurity in ITER-FEAT

Murakami, Yoshiki*; Amano, Tsuneo*; Shimizu, Katsuhiro; Shimada, Michiya; Ogawa, Yuichi*

JAERI-Research 2001-049, 58 Pages, 2001/11

JAERI-Research-2001-049.pdf:3.11MB

no abstracts in English

Journal Articles

Prediction of performance in ITER-FEAT

Matsumoto, Hiroshi; Barabaschi, P.*; Murakami, Yoshiki*

Fusion Technology, 40(1), p.37 - 51, 2001/07

 Times Cited Count:3 Percentile:27.11(Nuclear Science & Technology)

Recently, technical objectives of ITER were redefined aiming at the cost reduction of about 50% from the 1998 ITER design. Machine parameters which would satisfy the revised technical requirements under the engineering constraints were specified using a system code. The performance of these machines were studied and compared. As a result of these studies, final machine parameters were determined with revised conservative physics assumptions. This machine is referred as ITER-FEAT. It was shown that ITER-FEAT would achieve Q=10 in inductive operation with reasonable and conservative assumptions. Also, with an efficient current drive system and modest confinement improvement, possibility of Q=5 non-inductive operations in a steady state was shown.

Journal Articles

Performance assessment of ITER-FEAT

Murakami, Yoshiki*; Senda, Ikuo; Chudnovskiy, A.*; Vayakis, G.*; Polevoi, A. R.*; Shimada, Michiya

Purazuma, Kaku Yugo Gakkai-Shi, 73(7), p.712 - 729, 2001/07

no abstracts in English

JAEA Reports

Physics design of advanced steady-state tokamak reactor A-SSTR 2

Nishio, Satoshi; Ushigusa, Kenkichi; Ueda, Shuzo; Polevoi, A.*; Kurita, Genichi; Tobita, Kenji; Kurihara, Ryoichi; Hu, G.; Okada, Hidetoshi*; Murakami, Yoshiki*; et al.

JAERI-Research 2000-029, 105 Pages, 2000/10

JAERI-Research-2000-029.pdf:4.19MB

no abstracts in English

Journal Articles

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Sako, Kiyoshi*; Takase, Kazuyuki; Seki, Yasushi; Adachi, Junichi*; Yamazaki, Seiichiro*; et al.

Fusion Engineering and Design, 48(3-4), p.271 - 279, 2000/09

 Times Cited Count:16 Percentile:72.09(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Improved tokamak concept focusing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Kunugi, Tomoaki; Takase, Kazuyuki; Seki, Yasushi; Shinya, K.*; et al.

Fusion Engineering and Design, 41, p.357 - 364, 1998/00

 Times Cited Count:51 Percentile:95.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Parametric analysis and operational performance of EDA-ITER

*; Fujieda, Hirobumi*; Tsunematsu, Toshihide

JAERI-M 94-080, 151 Pages, 1994/06

JAERI-M-94-080.pdf:2.88MB

no abstracts in English

Journal Articles

Optimization of steady-state and hybrid operations in a tokamak fusion reactor by using divertor scaling models

*; Sugihara, Masayoshi

Fusion Technology, 24, p.375 - 390, 1993/12

no abstracts in English

JAEA Reports

Comparison between a steady-state fusion reactor and an inductively driven pulse reactor; Study as a power plant

Horiike, Hiroshi*; Kuroda, Toshimasa*; *; Sugihara, Masayoshi; Matsuda, Shinzaburo

JAERI-M 93-208, 31 Pages, 1993/10

JAERI-M-93-208.pdf:0.91MB

no abstracts in English

JAEA Reports

Tokamak plasma power balance calculation code(TPC code) outline and operation manual

Fujieda, Hirobumi*; *; Sugihara, Masayoshi

JAERI-M 92-178, 133 Pages, 1992/11

JAERI-M-92-178.pdf:2.3MB

no abstracts in English

JAEA Reports

Optimization for steady-state and hybrid operations of ITER by using scaling models of divertor heat load

*; Fujieda, Hirobumi*; Itami, Kiyoshi; Sugihara, Masayoshi

JAERI-M 92-145, 46 Pages, 1992/09

JAERI-M-92-145.pdf:1.32MB

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

16 (Records 1-16 displayed on this page)
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