Plasma and Fusion Research
Volume 6, 1405146 (2011)
Regular Articles
- National Institute for Fusion Science, Toki, Gifu 509-5292, Japan
Abstract
Corrosion characteristics of hydrogen-permeation materials (e.g., Pd-Ag, pure V, Nb, and Ta) are examined in molten salt Flinak, in order to develop a hydrogen-recovery section for a Flinak forced convection loop “Operational Recovery of Separated Hydrogen and Heat Inquiry -1 (Orosh2 i-1).” It is determined that their corrosion rate is not significant at 873 K under static conditions, compared with that of JLF-1 ferritic steel. However, pure V indicates a relatively high weight gain, likely due to O absorption. Dissolution of highly radioactive elements (e.g., Ag and Nb) is also indicated. The corrosion mechanisms and characteristics of the constituent elements are analyzed.
Keywords
liquid breeder blanket, Flibe, Flinak, palladium-silver, group 5 elements
Full Text
References
- [1] A. Sagara et al., Fusion Eng. Des. 81, 2703 (2006).
- [2] S. Fukada et al., Fusion Sci. Technol. 41, 1054 (2002).
- [3] S. Fukada et al., Fusion Eng. Des. 81, 477 (2006).
- [4] M. Kondo et al., The 9th Intl. Sympo. Fusion Nucl. Technol. (ISFNT-9), Oct. 11-16, 2009, Dalian China.
- [5] S. Yamauchi, Netsu Sokutei 12, 142 (1985) (in Japanese).
- [6] H. Yokokawa, Netsu Sokutei 12, 144 (1985) (in Japanese).
- [7] R.C. Svedberg and R.W. Buckman, Jr., Intel. Met. Rev. 25, 223 (1980).
- [8] D.L. Harrod et al., Intl. Met. Rev. 25, 163 (1980).
- [9] E.T. Cheng et al., J. Nucl. Mater. 258-263, 1767 (1998).
- [10] Y. Wu et al., J. Nucl. Mater. 307-311, 1026 (2002).
This paper may be cited as follows:
Takuya NAGASAKA, Masatoshi KONDO, Akio SAGARA and Takeo MUROGA, Plasma Fusion Res. 6, 1405146 (2011).