[Table of Contents]

Plasma and Fusion Research

Volume 10, 3405035 (2015)

Regular Articles


Potential of Copper Alloys using a Divertor Heat Sink in the Helical Reactor FFHR-d1 and their Brazing Properties with Tungsten Armor by using the Typical Candidate Filler Materials
Masayuki TOKITANI, Suguru MASUZAKI, Yutaka HIRAOKA1), Hiroyuki NOTO, Hitoshi TAMURA, Teruya TANAKA, Takeo MUROGA, Akio SAGARA and FFHR Design Group
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
1)
Department of Applied Physics, Okayama University of Science, 1-1 Ridai-cho, Okayama 700-0005, Japan
(Received 25 November 2014 / Accepted 17 February 2015 / Published 16 April 2015)

Abstract

A tungsten block is supposed to be used as a divertor armor material on the helical reactor FFHR-d1. On the other hand, material selection of the heat sink and bonding technique between armor and heat sink are currently under investigation. On the material selection, copper alloy has a large advantage for the thermal conductivity, but its material properties such as toughness and thermal conductivity, are dramatically decreased due to the neutron irradiation. However, from the assessment of the neutronics environment on the divertor region of the FFHR-d1, copper alloys could be used for a heat sink especially at the outer divertor. In the ITER case, copper alloy (CuCrZr) pipes are joined by a brazing technique with Nicuman37 filler material. This combination has not been optimized for the FFHR-d1, because the toughness of the CuCrZr at high temperature over 450 °C is dramatically decreased with increasing the temperature. As such, another candidate is an oxide dispersion-strengthened copper alloy (ODS-Cu) such as GlidCop®. For the bonding technique, a reliable brazing combination between “two kinds of copper alloys” and “three kinds of filler materials (MBF-20, BNi-6, Nicuman37)” were investigated from a viewpoint of mechanical strength. The most superior fracture strength among the three filler materials was BNi-6 with GlidCop®.


Keywords

copper alloy, tungsten, brazing, neutron irradiation

DOI: 10.1585/pfr.10.3405035


References

  • [1] S. Suzuki et al., Fusion Eng. Des. 81, 93 (2006).
  • [2] S.J. Zinkle and S.A. Fabritsiev, DOE/ER-0313/16 (1994).
  • [3] T. Tanaka et al., Fusion Eng. Des. 89, 1939 (2014).
  • [4] S. Suzuki et al., J. Plasma Fusion Res. 87, No.9, 607 (2011).
  • [5] A. Komori et al., Fusion Sci. Technol. 58, 1 (2010).
  • [6] A. Sagara et al., Fusion Eng. Des. 87, 594 (2012).
  • [7] T. Goto et al., Plasma Fusion Res. 7, 2405084 (2012).
  • [8] J. Miyazawa et al., Nucl. Fusion 52, 123007 (2012).
  • [9] S. Masuzaki et al., Nucl. Fusion 42, 750 (2002).
  • [10] K. Tobita et al., Fusion Eng. Des. 81, 1151 (2006).
  • [11] B.N. Sing et al., J. Nucl. Mater. 238, 244 (1996).
  • [12] S.A. Fabritsiev et al., Fusion Eng. Des. 36, 505 (1997).
  • [13] S. Ishino et al., J. Nucl. Mater. 283-287, 215 (2000).
  • [14] F.A. Garner et al., J. Nucl. Mater. 191-194, 386 (1992).
  • [15] D.J. Edwards et al., J. Nucl. Mater. 191-194, 416 (1992).
  • [16] T. Muroga et al., J. Nucl. Mater. 258-263, 955 (1998).

This paper may be cited as follows:

Masayuki TOKITANI, Suguru MASUZAKI, Yutaka HIRAOKA, Hiroyuki NOTO, Hitoshi TAMURA, Teruya TANAKA, Takeo MUROGA, Akio SAGARA and FFHR Design Group, Plasma Fusion Res. 10, 3405035 (2015).