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1Oarai Nuclear Engineering Institute, Japan Atomic Energy Agency, Japan
2J-PARC Center, Japan Atomic Energy Agency, Japan
3Michigan State University, United States of America
Submission: May 01, 2025;Published: June 17, 2025
	
 ISSN : 2576-8840Volume21 Issue 5
316FR steel, a modification of 316 austenitic stainless steel, will be used as a structural material in the sodium cooled fast reactor (SFR), one of the initiatives being developed in Japan to achieve carbon neutrality in order to combat global warming. To withstand the high-temperature operating environment of the SFR, the alloy design of the 316FR steel has been optimized to have high creep strength for a long time with controlled precipitation by optimizing the alloy composition. In order to clarify that 316FR steel can maintain its properties under the high temperature (around 550 °C) irradiation environment of the SFR, the authors mainly conducted in-situ observations under electron beam irradiation at high temperatures to investigate in detail the irradiation effects on the precipitates (mainly carbides), which are characteristic of 316FR steel. As a result, it was found that the precipitates in 316FR steel are more stable than those in type 304 stainless steel under irradiation without coarsening at grain boundaries or within grains. The characteristics and attractiveness of 316FR steel, the results obtained, and the mechanism of creep behavior under irradiation are also explained.
Keywords:316FR steel; 304 steel; Austenitic stainless steel; Electron beam irradiation; Irradiation damage; Creep strength; Precipitates; Precipitates on grain boundaries
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