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Journal Articles

Heating, current drive, and advanced plasma control in JFT-2M

Hoshino, Katsumichi; Yamamoto, Takumi; Tamai, Hiroshi; Oasa, Kazumi; Kawashima, Hisato; Miura, Yukitoshi; Ogawa, Toshihide; Shoji, Teruaki*; Shibata, Takatoshi; Kikuchi, Kazuo; et al.

Fusion Science and Technology, 49(2), p.139 - 167, 2006/02

 Times Cited Count:2 Percentile:81.1(Nuclear Science & Technology)

The main results obtained by the various heating and current drive systems, external coil system and divertor bias system are reviewed from the viewpoint of the advanced active control of the tokamak plasma. Also, the features of each system are described. The contribution of the JFT-2M in these areas are summarized.

Journal Articles

Study of SOL/divertor plasmas in JFT-2M

Kawashima, Hisato; Sengoku, Seio; Uehara, Kazuya; Tamai, Hiroshi; Shoji, Teruaki*; Ogawa, Hiroaki; Shibata, Takatoshi; Yamamoto, Masahiro*; Miura, Yukitoshi; Kusama, Yoshinori; et al.

Fusion Science and Technology, 49(2), p.168 - 186, 2006/02

 Times Cited Count:2 Percentile:81.1(Nuclear Science & Technology)

Experimental efforts on JFT-2M have been devoted to understand SOL/Divertor plasmas and to investigate power and particle controllability. Open divertor configuration was used for the first decade of JFT-2M started in 1984. We found out the SOL/Divertor plasma properties such as in/out asymmetry, heat and particle diffusivities, and SOL current at ELMs. Handling of power and particle was demonstrated by active control methods such as local pumping, edge ergodization, divertor biasing, and edge heating. For improvement of power and particle control capability of divertor, it was modified to closed configuration in 1995, which demonstrated the baffling effects with narrower divertor throat. Dense and cold divertor state (n$$_{e}$$$$^{div}$$ = 4$$times$$10$$^{19}$$ m$$^{-3}$$ and T$$_{e}$$$$^{div}$$ = 4 eV), compatible with the improved confinement modes (e.g. H-mode), was realized by strong gas puffing. Being related with the core confinement at H-mode, the edge plasma fluctuations were identified by an electrostatic probe. These are reviewed in this paper.

JAEA Reports

Study for characteristic of dynamic analysis models for tokamak complex of International Thermonuclear Experimental Reactor (ITER)

Nakakura, Kensuke*; Yagenji, Akira*; Shoji, Teruaki*; Araki, Masanori; Neyatani, Yuzuru; Tanaka, Eiichi*; Shima, Hiroaki*

JAERI-Tech 2005-058, 61 Pages, 2005/09

JAERI-Tech-2005-058.pdf:4.49MB

The design of International Thermonuclear Experimental Reactor (ITER) had been done during the period of Engineering Design Activities (EDA) and its final deign report was published on July 2001. After that the further design studies have been performed as activities in the CTA and ITA periods. As for Tokamak complex, Japan Atomic Energy Research Institute (JAERI) performed preliminary study for both static and dynamic analyses with a few types of analysis models based on the Technical Guidelines for Aseismic Design of Nuclear Power Plants etc during EDA. In comparison with reactor building for nuclear fission power plant, its outside is not so different from reactor building's one. However, its structural characteristics inside building are apparently different from reactor building's one, because the bio shield of Tokamak complex has a lot of large penetration of ports. Therefore, characteristic of dynamic analysis models for Tokamak complex needs to be evaluated in order to perform the detailed design of Tokamak complex in account for site-dependent conditions. This report describes results of characteristic evaluation with representative analytical models for Tokamak complex, which are modeled with Finite Element Method and Lumped mass, and it is confirmed that adopted evaluation method of the bio shield wall and floor's stiffnesses around the bio shield wall for Lumped mass model is adequate.

JAEA Reports

Revised version of tokamak transient simulation code SAFALY, 2

Senda, Ikuo*; Fujieda, Hirobumi; Neyatani, Yuzuru; Tada, Eisuke; Shoji, Teruaki

JAERI-Data/Code 2003-012, 73 Pages, 2003/07

JAERI-Data-Code-2003-012.pdf:3.45MB

The tokamak transient simulation code, named SAFALY, was revised recently and the sensitivity analyses on the parameters in the code were carried out. This report is composed of two volumes. The formulation and the parameters in modeling the plasma and in-vessel components are described in the first volume. In this second volume, the results of the sensitivity studies are reported. The sensitivity studies were performed in two steps. In the first step, the responses of plasmas in the occurrence of plasma disturbances were analyzed for various initial conditions. For each disturbance, the initial condition of the plasma, which gave the largest increase of the fusion power, was identified. In the second step, by using initial conditions derived in the first step, the sensitivities of plasma reactions with respect to variation of the parameters in SAFALY code were analyzed. In the analyses, the increase of the fueling, the increase of the plasma confinement improvement factor and the increase of the auxiliary heating power were considered as plasma disturbances.

JAEA Reports

Revised version of tokamak transient simulation code SAFALY, 1

Senda, Ikuo*; Fujieda, Hirobumi; Neyatani, Yuzuru; Tada, Eisuke; Shoji, Teruaki

JAERI-Data/Code 2003-008, 37 Pages, 2003/06

JAERI-Data-Code-2003-008.pdf:1.58MB

Tokamak transient simulation code, named SAFALY, was revised. SAFALY code has been developed to simulate transient events in Tokamaks. Modeling of the plasma and algorithms of the simulation were revised. The code was also modified to deal with the variation of the plasma current. The code was improved to allow flexible modeling of in-vessel components. The data transfer between SAFALY and related codes was arranged to prepare data required in analyses with SAFALY, such as the distributions of heat/neutron loads and the radiation form factor between in-vessel components. The report is composed of two volumes. The formulation and the parameters in modeling plasma and in-vessel components are described in this first volume. Examples of simulation results, using the design of ITER-FDR in 2001, are presented and general properties of plasmas' responses with respect to perturbations are discussed. The results of the sensitivity studies with respect to simulation parameters and initial conditions will be reported in the second volume.

JAEA Reports

Alternatives of ITER vacuum vessel support system

Omori, Junji*; Kitamura, Kazunori*; Araki, Masanori; Oono, Isamu*; Shoji, Teruaki

JAERI-Tech 2002-053, 86 Pages, 2002/07

JAERI-Tech-2002-053.pdf:3.81MB

no abstracts in English

Journal Articles

Linear evolution of plasma equilibrium in tokamaks

Senda, Ikuo; Shoji, Teruaki; Tsunematsu, Toshihide

Nuclear Fusion, 42(5), p.568 - 580, 2002/05

 Times Cited Count:4 Percentile:84(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

The Summary report on engineering design activities in the International Thermonuclear Experimental Reactor (ITER) project

Mori, Masahiro; Shoji, Teruaki; Araki, Masanori; Saito, Keiji*; Senda, Ikuo; Omori, Junji*; Sato, Shinichi*; Inoue, Takashi; Oono, Isamu*; Kataoka, Takahiro*; et al.

Nippon Genshiryoku Gakkai-Shi, 44(1), p.16 - 89, 2002/01

no abstracts in English

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

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:100

no abstracts in English

Journal Articles

Design analysis on the magnetic field control system in compact ITER

Senda, Ikuo; Shoji, Teruaki; Araki, Masanori; ITER Japan Home Team; ITER Joint Central Team

International Journal of Applied Electromagnetics and Mechanics, 13(1-4), p.349 - 357, 2001/00

no abstracts in English

Journal Articles

Simulation studies of plasma initiation and disruption in JT-60U

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; Matsukawa, Makoto; Ushigusa, Kenkichi

Nucl. Eng. Des., 45(1), p.15 - 29, 1999/00

no abstracts in English

Journal Articles

Optimization of plasma initiation in the ITER tokamak

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

Fusion Engineering and Design, 42, p.395 - 399, 1998/00

 Times Cited Count:3 Percentile:65.86

no abstracts in English

Journal Articles

3-D electromagnetic transient characteristics of in-vessel components in tokamak reactor

Takase, Haruhiko; Senda, Ikuo; Araki, Masanori; Shoji, Teruaki; Tsunematsu, Toshihide

IAEA-CN-69/FTP/28, 4 Pages, 1998/00

no abstracts in English

Journal Articles

Divertor biasing effects to reduce L/H power threshold in the JFT-2M tokamak

Miura, Yukitoshi; *; *; Hoshino, Katsumichi; *; *; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.

Fusion Energy 1996, p.167 - 175, 1997/05

no abstracts in English

Journal Articles

Investigation of causality in the H-L transition on the JFT-2M tokamak

*; *; *; *; *; *; *; Oikawa, Toshihiro; *; *; et al.

Fusion Energy 1996, p.885 - 890, 1997/05

no abstracts in English

Journal Articles

Approximation of eddy currents in three dimensional structures by toroidally symmetric models,and plasma control issues

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

Nuclear Fusion, 37(8), p.1129 - 1145, 1997/00

 Times Cited Count:9 Percentile:64.42(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Fast ion confinement in JT-60U and implications for ITER

Tobita, Kenji; Hamamatsu, Kiyotaka; Harano, Hideki*; Nishitani, Takeo; Kusama, Yoshinori; Kimura, Haruyuki; Takizuka, Tomonori; Fujieda, Hirobumi*; Shoji, Teruaki; Senda, Ikuo*; et al.

Proc. of 5th IAEA Technical Committee Meeting on Alpha Particles in Fusion Research, p.45 - 48, 1997/00

no abstracts in English

JAEA Reports

Optimizing voltage wave forms of poloidal field coils at the plasma breakdown

Senda, Ikuo*; Shoji, Teruaki; *; Fujieda, Hirobumi*; Tsunematsu, Toshihide

JAERI-Tech 96-016, 23 Pages, 1996/03

JAERI-Tech-96-016.pdf:0.75MB

no abstracts in English

Journal Articles

Investigation of edge localized mode in the JFT-2M tokamak

Nagashima, Keisuke; Shoji, Teruaki; Miura, Yukitoshi

Nuclear Fusion, 36(3), p.335 - 345, 1996/00

 Times Cited Count:10 Percentile:61.15(Physics, Fluids & Plasmas)

no abstracts in English

54 (Records 1-20 displayed on this page)