2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2G07-10] Blanket Materials

Wed. Mar 27, 2024 11:00 AM - 12:00 PM Room G (21Bildg.3F 21-317)

Chair:Teruya Tanaka(NIFS)

11:30 AM - 11:45 AM

[2G09] Microstructural change in He-irradiated V-Cr-Ti alloys with low Ti addition

*YICHEN ZOU1, Ken-ichi FUKUMOTO2, Ryoya Ishigami3, Takuya Nagasaka4 (1. University of Fukui, graduate school of engineering, 2. RINE/ Univ. of Fukui, 3. The Wakasa Wan Energy Research Center, 4. National Institute for Fusion Science)

Keywords:vanadium alloy, irradiation hardening, He ion irradiation, Trans-mission electron microscopy

In this study, to investigate the change in strength due to low Ti modification of V alloys and the effects of irradiation on strength and dimensional stability, He ion irradiation was performed on V alloys with varying impurity concentrations and Ti, Cr addition levels. Observations of the microstructure were made using a transmission electron microscope (TEM), and measurements of irradiation hardening were conducted using a nanoindentation hardness tester. The study aimed to obtain guidelines for the development of V alloys based on the correlation between microstructure and strength after irradiation.

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