Thermal aging effects on high temperature tensile strength of Mod.9Cr-1Mo steel with stress release treatment

豊田 晃大; 今川 裕也; 鬼澤 高志; 鈴木 章裕*

Proceedings of the ASME 2025 Pressure Vessels & Piping Conference (PVP2025) (Internet), 8 Pages, 2025/07

https://doi.org/10.1115/PVP2025-153101

Sodium-cooled fast reactors (SFRs) have been focused on to realize a decarbonized society and are being developed in Japan. Since there is concern that Mod.9Cr-1Mo steel, a candidate material for SFR steam generators, will be affected by thermal aging and lose strength when used at high temperatures for long periods of time, it is important to evaluate the effect of thermal aging over long periods of time. Mod.9Cr-1Mo steel requires post weld heat treatment (PWHT) after welding. In the Japan Society of Mechanical Engineers (JSME)code, Rules on the Design and Construction of Nuclear Power Plants, the allowable values for base metal are set using materials that have undergone stress relief heat treatment (SR) after normalizing and tempering (NT) to simulate the thermal history of the PWHT. This paper describes the post aging tensile strength of materials subjected to prolonged thermal aging in order to provide a more detailed evaluation of the effects of thermal aging on Mod. 9Cr-1Mo steels subjected to NT+SR than has been done in the past. The evaluation in this paper used tensile test results of material that had been actually thermal aged at 550C for approximately 200,000 hours. The results of post aging tensile tests showed that there was a difference in strength loss after aging between the NT materials and NT+SR materials. This paper discusses the differences between NT materials and NT+SR materials from the tensile test results obtained and identifies issues that need to be resolved for further analysis.