Plasma and Fusion Research

Volume 12, 1405017 (2017)

Regular Articles


Cartridge-Type Helical Blankets Aiming at Easy Construction and Maintenance for the FFHR-d1
Junichi MIYAZAWA1,2), Hitoshi TAMURA1), Teruya TANAKA1,2), Takanori MURASE1), Takuya GOTO1,2), Nagato YANAGI1,2), Ryuichi SAKAMOTO1,2), Akio SAGARA1,2) and the FFHR Design Group
1)
National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
2)
SOKENDAI (The Graduate University for Advanced Studies), 322-6 Oroshi, Toki, Gifu 509-5292, Japan
(Received 26 December 2016 / Accepted 9 March 2017 / Published 16 May 2017)

Abstract

A new cartridge-type blanket named the CARDISTRY-B is proposed for the helical fusion reactor FFHR-d1. This blanket is composed of the neutron shield and the tritium breeder using molten salt. Both of these are toroidally segmented every two degrees. At each toroidal angle, the segmented parts are divided further into several cartridges in order to make it possible to assemble these cartridges after completion of the superconducting magnet coils. The neutron shield is basically assembled by using mortise and tenon prepared on each of the cartridges and the lower port, instead of the wide area welding. After assembly, the plasma side of the neutron shield is welded to form a vacuum vessel. Another side of the neutron shield facing on the superconducting magnet coils is covered with the thermal shield, which was already attached before assembly. The tritium breeder cartridges can be replaced without cutting or welding of cooling pipes inside the vacuum vessel, where severe radiation dose is expected. Details of the CARDISTRY-B, including the results of motion analysis for all cartridges and estimation of the cartridge weight, are discussed.


Keywords

heliotron, fusion reactor, tritium-breeding blanket, neutron shield, thermal shield, toroidal segmentation, LHD, FFHR, REVOLVER-D, CARDISTRY-B

DOI: 10.1585/pfr.12.1405017


References

  • [1] A. Sagara et al., Fusion Eng. Des. 89, 2114 (2014).
  • [2] A. Sagara et al., 2016 IAEA Fusion Energy Conf., Kyoto, Japan, FIP/3-4Ra, submitted to Nucl. Fusion. https://conferences.iaea.org/indico/event/98/session/40/contribution/204/material/paper/0.pdf
  • [3] A. Komori et al., Fusion Sci. Tech. 58, 1 (2010).
  • [4] J. Miyazawa et al., Plasma Fusion Res. 7, 2402072 (2012).
  • [5] N. Yanagi et al., Cryogenics 80, 243 (2016).
  • [6] J. Miyazawa et al., 2016 IAEA Fusion Energy Conf., Kyoto, Japan, FIP/P7-2. https://conferences.iaea.org/indico/event/98/session/31/contribution/16/material/paper/0.pdf
  • [7] T. Tanaka et al., Plasma Fusion Res. 7, 2405132 (2012).
  • [8] T. Tanaka et al., Fusion Eng. Des. 87, 584 (2012).
  • [9] H. Tamura et al., Fusion Eng. Des. 88, 2033 (2013).
  • [10] T. Goto et al., Plasma Fusion Res. 11, 2405047 (2016).
  • [11] J. Moon et al., Metall. Mater. Trans. A 46A, 156 (2015).
  • [12] H. Fu et al., Plasma Fusion Res. 10, 3405015 (2015).