プラズマ核融合学会誌１１月【８１‐１１】／小特集５

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1 Japan Atomic Energy Agency, Ibaraki , Japan 1) Kyoto University, Uji , Japan 2) National Institute of Advanced Industrial Science and Technology, Tsukuba , Japan 3) Central Research Institute of Electric Power Industry, Tokyo , Japan corresponding author s [email protected]

3 et al. Fig. 1 Simulation results of world electricity generated till 2100 under IPCC SRES-A1B scenario for BAU (a) and 550 ppmv (b).

4 et al., Climate Change 2001: Mitigation et al., et al., 19th World Energy Conference, 5 9 September 2004, Special Rreport on Eemission Sscenarios et al.,

5 et al.

7 et al.

8 Fig. 2 Estimation of tokamak reactor weight for various values. The weight in shade ( 5,000 t) corresponds to the primary system of LWR.

9 et al. Fig. 3 Schematic drawing of field lines on magnetic surface for high and low aspect ratio configurations. Fig. 4 Dependence of achievable k and b N on A

10 Fig. 5 Dependence of achievable b N on the conducting wall position (r w/a)ina=2.44, 3.26 and 4.2 cases Fig. 6 Reactor weight and weight power density of VECTOR in comparison with conventional tokamak reactors

11 et al. Fig. 8 Basic concept for high beta plasmas due to the plasma profile control. Fig. 7 Schematic reactor configuration for low-a reactor. Low-A is favorable for sector transport / hot cell maintenance.

12 Fig. 9 Measured (solid) and target profiles (broken) for q, and Te after projection on the set of basis functions, for pulse # for Te, the original profile has also been plotted (dotted). Each column corresponds to one time, respectively, t =5.5s(startofcontrol),t =8sandt = s (end of control)[27]. Fig. 10 (a) Time evolution of T i gradient with the combination of NB. (b) Momentum source profiles in the different directions of toroidal momentum injection. Profiles of (c) ion temperature and (d) toroidal rotation velocity in the active ITB control discharge by changing the direction of toroidal momentum injection[29].

13 et al. q et al., et al., et al., et al., et al., et al., et al., et al., Submitted to Proceedings of 19th ICNSP and 7th APPTC in Nara, et al., 17th IAEA Fusion Energy Conf., Yokohama, et al., 20th IAEA Fusion Energy Conf., Vilamoura, et al. Proc. 14th Int. Conf. of Plasma Physics and Controlled Nuclear Fusion Research, et al., et al., et al., et al., et al., Proc. 18th IAEA Fusion Energy Conf., Sorrento, et al., et al., et al., et al., et al., et al., Proc. 20th IAEA Fusion Energy Conf., et al., et al., et al., et al., Proc. 18th IAEA Fusion Energy Conf., et al.,

15 et al. Fig. 11 (A) (B) Reactor Configurations for In-situ Maintenance and Hot Cell Maintenance. (A) In-situ Maintenance, (B) Hot Cell maintenance.

17 et al. et al., et al., et al., et al., et al.,

The Plasma Boundary of Magnetic Fusion Devices

ASAKURA Nobuyuki, Japan Atomic Energy Research Institute, Naka, Ibaraki 311-0193, Japan e-mail: [email protected] The Plasma Boundary of Magnetic Fusion Devices Naka Fusion Research Establishment,