Pellet injection algorithm for the FFHR helical reactor

Fusion Engineering and Design

Volumn 70, Issue 3, 2004, Pages 247-267

  Mitarai, O ^a   Oda, A ^b   Sagara, A ^c   Yamazaki, K ^c   Motojima, O ^c  

^a TOKAI UNIVERSITY   (Japan)

^b KUMAMOTO NATIONAL COLLEGE OF TECHNOLOGY   (Japan)

^c NATIONAL INSTITUTE FOR FUSION SCIENCE   (Japan)

Author keywords

Force free helical reactor; Pellet injection algorithm; Plasma parameters

Indexed keywords

ALGORITHMS; FUSION REACTIONS; FUSION REACTORS; HELIUM; IGNITION; NATURAL FREQUENCIES; OSCILLATIONS; PARAMETER ESTIMATION; PELLETIZING; PLASMAS; SIGNAL PROCESSING;

FORCE AND HELICAL REACTORS; HELICAL REACTORS; PELLET INJECTION ALGORITHMS; PLASMA PARAMETERS;

NUCLEAR REACTORS;

EID: 3142754368     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2004.02.001     Document Type: Article

References (24)

1. Iiyoshi A., et al. Fusion Technol. 17:1990;169.
2. Sagara A., et al. Blanket and divertor design for force free helical reactor (FFHR). Fusion Eng. Design. 29:1995;51.
3. Sagara A., et al. Design studies of helical-type fusion reactor FFHR. Fusion Eng. Design. 41:1998;349.
4. Sagara A., Motojima O., Imagawa S., Mitarai O., et al. Design studies of helical-type fusion reactor FFHR. Fusion Eng. Design. 41(Part B):1998;349.5.
5. A. Sagara, K. Yamazaki, et al., LHD-type compact helical reactors, in: Proceedings of the 17th IAEA Fusion Energy Conference, Yokohama, FTP-3, 1998.
6. Sakamoto R., Yamada H., et al. Impact pellet injection on extension of the operational region in LHD. Nucl. Fusion. 41:2001;381.
7. Schuster E., Slavkrstic' M., Tunan G. Burn control in fusion reactors via nonlinear stabilization techniques. Fusion Sci. Technol. 43:2003;18.
8. Motojima O., Yamada H., Komori A., Ohyabu N., et al. Initial physics achievements of large helical device experiments. Phys. Plasmas. 6:1999;1843.
9. Erckmann V., Wagner F., Baldzuhn J., Braket R., Burhenn R., et al. H mode of the W 7-AS Stellarator. Phys. Rev. Lett. 70:1993;2086.
10. Toi K., Ohdachi S., Yamamaoto S., et al. Nucl. Fusion. 44:2004;217.
11. Sudo S., Takeiri Y., Zushi H., Sano F., Itoh K., Kondo K., Iiyoshi A. Scalings of energy confinement and density limit in Stellarator/Heliotron devices. Nucl. Fusion. 30:1990;11.
12. Stroh U., Murakami M., Dory R.A., Yamada H., Okamura S., Sano F., Obiki T. Energy confinement scaling from International Stellarator Database. Nucl. Fusion. 36:1996;1063.
13. Mitarai O., Muraoka K. A proposed set of diagnostics for core ignition burn control in a Tokamak reactor. Nucl. Fusion. 39:1999;725.
14. Mitarai O., Muraoka K. Analyses of diagnostic failure effect and fail-safe ignited operation in a Tokamak fusion reactor. Fusion Technol. 36:1999;194.
15. O. Mitarai, Fuel ratio and fueling control for safe ignited operation in ITER class Tokamak reactors, in: G. Francois (Ed.), Advances in Plasma Physics Research-II, Nova Science Publishers, 2002, p. 37.
16. Viniar I., Sudo S., Geraud A. Pellet injectors developed at the PELIN laboratory for international projects. Fusion Eng. Design. 56-59:2001;295.
17. Viniar I. A new centrifuge pellet injector with a screw extruder for steady state fueling. J. Plasma Fusion Res. Ser. 3:2000;467.
18. Sagara A., Yamanishi H., Uda T., Motojima O., Mitarai O., et al. Studies on flibe blanket designs in helical reactor FFHR. Fusion Technol. 39(2 (Part 2)):2001;753.
19. Painter S.L., Lyon J.F. Alpha-particle losses in compact Torsatron reactors. Fusion Technol. 16:1989;157.
20. T. Watanabe, Journal of Plasma and Fusion Research, vol. 74 (suppl.), Large Helical Device (LHD) Project, 1998, p. 267 (in Japanese).
21. McCormick K., Grigull P., Burhenn R., et al. New advanced operational regime on the W7-AS Stellarator. Phy. Rev. Lett. 89:2002;015001.
22. Maingi R., Jacson G.L., et al. Control of wall particle inventory with divertor pumping on DIII-D. Nucl. Fusion. 36:1996;245.
23. Baylor L.R., Geraud A., et al. International pellet ablation database. Nucl. Fusion. 37:1997;445.
24. Yamazaki K., Amano T. Plasma transport simulation for helical confinement systems. Nucl. Fusion. 32:1992;633.