Plasma and Fusion Research
Volume 6, 2405117 (2011)
Regular Articles
- Tokai university, 4-1-1 Kitakaname, Hiratuka 259-1292, Japan
- 1)
- The graduate university for advanced studies, 322-6 Oroshi-cho, Toki 509-5292, Japan
- 2)
- National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
Abstract
The development of functional layers such as a tritium permeation barrier and an anti-corrosion layer is the essential technology for the development of a molten salt type self cooled fusion blanket. In the present study, the characteristics of a nitriding treatment on a reduced activation ferritic steel, JLF-1 (Fe-9Cr-2W-0.1C) as the functional layer were investigated. The steel surface was nitrided by an ion nitriding treatment or a radical nitriding treatment. The nitridation characteristic of the steel surface was made clear based on the thermodynamic stability. The thermal diffusivity, the hydrogen permeability and the chemical stability in the molten salt Flinak were investigated. The results indicated that the nitriding treatment can improve the compatibility in the Flinak without the decrease of the thermal diffusivity, though there was little improvement as the hydrogen permeation barrier.
Keywords
coating, nitriding, blanket, corrosion, molten salt, FFHR
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References
- [1] A. Sagara et al., Fus. Sci. and Tech. 47, 524 (2005).
- [2] T. Watanabe et al., J. Plasma Fusion Res. SERIES 9, 342 (2010).
- [3] H. Hishinuma et al., J. Nucl. Mater., in press (2011).
- [4] D. Zhang et al., Fus. Eng. and Design, in press (2011).
- [5] M. Kondo et al., Fus. Eng. and Design 85, 1430 (2010).
- [6] K. Fukada, Journal of the JSTP, vol.40, 13 (1999).
- [7] W.J. Parker, R.J. Jenkins, C.P. Butler and G.L. Abbot, Journal of applied physics 32, 1679 (1961).
- [8] D. Zhang, T. Tanaka and T. Muroga, J. Nucl. Mater., in press (2011).
This paper may be cited as follows:
Masatoshi KONDO, Takashi WATANABE, Teruya TANAKA, Dongxun ZHANG and Akio SAGARA, Plasma Fusion Res. 6, 2405117 (2011).