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A low wall-loading DEMO reactor design with high priority for early and reliable realization of a tokamak fusion reactor over the cost performance

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Abstract

Based on scientific databases adopted for designing ITER plasmas and on the advancement of fusion nuclear technology from the recent R&D program, a low wall-loading DEMO fusion reactor has been designed, where high priority has been given to the early and reliable realization of a tokamak fusion plasma over the cost performance. Since the major radius of this DEMO reactor is chosen to be 10 m, plasma ignition is achievable with a low fusion power of 0.8 GW and an operation period of 4–5 hours is available only with inductive current drive. The low ignition power makes it possible to adopt a first wall with an austenitic stainless steel, for which significant databases and operating experience exists, due to its use in the presence of neutron irradiation in fission reactors. In step with development of advanced materials, a step-wise increase of the fusion power seems to be feasible and realistic, because this DEMO reactor has the potential to produce a fusion power of ∼5 GW.

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References

  1. ITER Joint Central Team and Home Teams (1994). The ITER EDA Outline Design. Proc. on 15th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Seville, Spain, Sept. 26–Oct. 1, IAEA-CN-60/E-1-1-1 ∼ E-P-13.

  2. F. Najmabadi and The STARLITE Team (1995). Overview and Initial Results of Starlite Project. Proc. of the Japan-U.S. Workshop on Fusion Power Reactors, March 13–16, Kyoto, Japan.

  3. W. M. Stacey (1994). Extrapolation to a Demonstration Reactor from the ITER and Advanced Physics and Materials Databases. Proc. on 15th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Seville, Spain, Sept. 26–Oct. 1 IAEA-CN-60/F-P-5.

  4. S. O. Dean, C. C. Baker, J. Galambos, Y-K. M. Peng, J. Sheffield, D. Cohn, L. Bromberg, E. A. Chaniotakis, D. P. Dautovich, P. Gierszewski, W. Morison, W. R. Ellis, and B. B. Kadomtsev (1992). Pilot Plant: A Shortened Path to Fusion Power. Proc. on 14th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Würzburg, Germany, Sept. 30–Oct. 7, IAEA-CN-56/G-1-5.

  5. M. A. Abdou, M. Peng, S. Berk, A. Ying, M. Tillack, F. Tehranian, B. Hooper, O. G. Filatov, A. B. Mineev, and V. V. Filatov (1994). Requirements and Design Envelope for Volumetric Neutron Source Fusion Facilities for Fusion Nuclear Technology Development. Proc. on 15th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Seville, Spain, Sept. 26–Oct. 1, IAEA-CN-60/F-2-II-6-1.

  6. N. Inoue, Y. Ogawa, T. Yamamoto, Z. Yoshida, K. Okano, and A. Hatayama (1992). Feasibility Study on Inductively Operated Day-Long Tokamak Reactor. Proc. on 14th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Würzburg, Germany, Sept. 30–Oct. 7, IAEA-CN-56/G-1-4.

  7. Y. Ogawa, K. Okano, N. Inoue, J. F. Wang, T. Yamamoto, Z. Yoshida, A. Hatayama, and T. Amano (1994). Advanced Design of a Pulsed Tokamak Fusion Reactor. Proc. on 15th Int. Conf. on Plasma Phys. and Contr. Nucl. Fusion Res., Seville, Spain, Sept. 26–Oct. 1, IAEA-CN-60/F-P-8.

  8. N. Inoue and Y. Ogawa (1993). Rationale for conceptual design study of ultra-long-pulse tokamak fusion reactor.J. Plasma Fusion Res.,69, 313.

    Google Scholar 

  9. A. Kohyama, Y. Kohno, K. Asakura, M. Yoshino, C. Namba, and C. R. Eiholzer (1994). Irradiation creep of low-activation ferritic steels in FFTF/MOTA.J. Nucl. Mater.,212–215, 751.

    Google Scholar 

  10. T. C. Hender, R. Fitzpatrick, A. W. Morris, P. G. Carolan, R. D. Durst, T. Edlington, J. Ferreira, S. J. Fielding, P. S. Haynes, J. Hugill, I. J. Jenkins, R. J. LaHaye, B. J. Parham, D. C. Robinson, T. N. Todd, M. Valovic, and G. Vayakis (1992). Effect of resonant magnetic perturbations on Compass-C tokamak discharges.Nucl. Fusion,32, 2091.

    Google Scholar 

  11. A. Kohyama, M. L. Grossbeck, and G. Piatti (1992). The application of austenitic stainless steels in advanced fusion systems: Current limitations and future prospects.J. Nucl. Mater. 191–194, 37.

    Google Scholar 

  12. S. Shikakura, S. Ukai, Y. Sato, M. Harada, S. Koyama, T. Ito, S. Nomura, and I. Shibahara (1994). Development of advanced austenitic stainless steel for fast reactor core material.J. Atomic Energy Soc Japan,36, 441.

    Google Scholar 

  13. N. A. Uckan and ITER Physics Group (1990). ITER Physics Design Guidelines: 1989. ITER Documentation Series, No. 10, International Atomic Energy Agency, Vienna.

    Google Scholar 

  14. ITER (1991). ITER Physics. ITER Documentation Series, No. 21, International Atomic Energy Agency, Vienna.

    Google Scholar 

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Ogawa, Y., Inoue, N., Wang, J. et al. A low wall-loading DEMO reactor design with high priority for early and reliable realization of a tokamak fusion reactor over the cost performance. J Fusion Energ 14, 353–359 (1995). https://doi.org/10.1007/BF02214513

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