Compatibility of zirconium alloys in high-temperature sodium

Furukawa, Tomohiro ; Kato, Shoichi ; Maeda, Shigetaka ; Yamamoto, Masaya; Sekine, Takashi ; Ito, Chikara

Application of zirconium alloy as a neutron reflector around the driver fuel region of the Japanese experimental fast reactor JOYO has been planned for a further increase of core average burn-up. In order to investigate the compatibility of the zirconium alloys with high-temperature sodium which is coolant of the JOYO, corrosion test in sodium and tensile test of the exposed alloys were performed. The corrosion test was done at 500 $^{circ}$ C and 650 $^{circ}$ C in stagnant/flowing sodium for two kinds of zirconium alloys, and then weight change measurement and metallurgical observation were carried out. The tensile test was performed in air at the same temperature with the sodium exposure.

Language	:	Japanese
Report No.	:	JAEA-Research 2011-039
Pages	:	20 Pages
Publication Year/Month	:	2012/02
Patent information	:
PDF	:	JAEA-Research-2011-039.pdf:3.4MB
Paper URL	:	https://doi.org/10.11484/jaea-research-2011-039
Keywords	:	no keyword
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:	Corrosion Behavior of Metals in Sodium; Compatibility of Zirconium Alloy with High-Temperature Sodium[/]
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Registration No. : RS20110039
JAEA Abstracts No. : 40000390

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