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Journal Articles

Progress in physics basis and its impact on ITER

Shimada, Michiya; Campbell, D.*; Stambaugh, R.*; Polevoi, A. R.*; Mukhovatov, V.*; Asakura, Nobuyuki; Costley, A. E.*; Donn$'e$, A. J. H.*; Doyle, E. J.*; Federici, G.*; et al.

Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11

This paper summarises recent progress in the physics basis and its impact on the expected performance of ITER. Significant progress has been made in many outstanding issues and in the development of hybrid and steady state operation scenarios, leading to increased confidence of achieving ITER's goals. Experiments show that tailoring the current profile can improve confinement over the standard H-mode and allow an increase in beta up to the no-wall limit at safety factors $$sim$$ 4. Extrapolation to ITER suggests that at the reduced plasma current of $$sim$$ 12MA, high Q $$>$$ 10 and long pulse ($$>$$1000 s) operation is possible with benign ELMs. Analysis of disruption scenarios has been performed based on guidelines on current quench rates and halo currents, derived from the experimental database. With conservative assumptions, estimated electromagnetic forces on the in-vessel components are below the design target values, confirming the robustness of the ITER design against disruption forces.

Journal Articles

Conceptual tokamak design at high neutron fluence

Araki, Masanori; Sato, Shinichi*; Senda, Ikuo; Omori, Junji*; Shoji, Teruaki

Fusion Engineering and Design, 58-59, p.887 - 892, 2001/11

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

High performance and current drive experiments in the JAERI Tokamak-60 Upgrade

Kondoh, Takashi; JT-60 Team

Physics of Plasmas, 1(5), p.1489 - 1496, 1994/05

 Times Cited Count:19 Percentile:56.82(Physics, Fluids & Plasmas)

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

Optimization of OH coil recharging scenario of quasi-steady operation in tokamak fusion reactor by lower hybrid wave current drive

; ; ; ; ; Iida, Hiromasa; ;

Nucl.Eng.Des./Fusion, 1, p.265 - 277, 1984/00

 Times Cited Count:2 Percentile:29.76(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

6 (Records 1-6 displayed on this page)
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