Suppression of irradiation hardening in tungsten-coated ferritic steel for fusion reactor blanket applications

被引:0
作者
Seki, Kotaro [1 ,2 ]
Yoshida, Kenta [2 ]
Miyata, Hotaka [1 ,2 ]
Hasegawa, Akira [2 ]
Kondo, Sosuke [2 ]
Yu, Hao [2 ]
Ogino, Yasuyuki [2 ]
Hokamoto, Kazuyuki [3 ]
Tanaka, Shigeru [3 ]
Koyanagi, Takaaki [4 ]
Kasada, Ryuta [2 ,5 ]
机构
[1] Tohoku Univ, Grad Sch Engn, Sendai, Japan
[2] Tohoku Univ, Inst Mat Res, Sendai, Japan
[3] Kumamoto Univ, Inst Ind Nanomat, Kumamoto 8608555, Japan
[4] Mat Sci & Technol Div, Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[5] Natl Inst Fus Sci, Toki 5095292, Japan
关键词
Irradiation hardening; Tungsten; Ferritic steel; Joining; Interface; Microstructure; Coating; Explosive welding; PURE TUNGSTEN; BEHAVIOR; MICROSTRUCTURE; EVOLUTION; F82H;
D O I
10.1016/j.jnucmat.2025.155657
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
W-coated reduced activation ferritic steels have been developed for use as plasma facing components in fusion reactor blankets, offering excellent sputtering resistance and structural strength. Previous high-temperature coating methods, such as diffusion bonding and brazing, caused interfacial deterioration due to thermal stress from mismatched thermal expansion between W and reduced activation ferritic steel. To address this, underwater explosive welding was introduced as a high-velocity cold process that joins dissimilar materials while maintaining a strong, thin interface without the thermal issues associated with traditional methods. In this study, the effects of neutron irradiation on the hardness and microstructure in W-coated F82H reduced activation ferritic steel (W/F82H) joined by underwater explosive welding are investigated. Following neutron irradiation at 290 degrees C, irradiation hardening is suppressed in W, F82H, and their interface within the W/F82H material. Furthermore, microstructural observations indicate that the recovery of work hardening and relaxation of elastic strain introduced during coating significantly contribute to the suppression of irradiation hardening in W/F82H. In conclusion, W/F82H exhibits significantly suppressed irradiation hardening compared with those in standalone materials. This suppression is explained by residual stress from thermal expansion mismatch and the unique microstructure at the interface. These results provide valuable insights for the development of more durable materials in nuclear fusion applications.
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页数:10
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