Oral presentation

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

[2L06-09] Structural Materials 2 (Refractory Materials)

Thu. Mar 18, 2021 10:55 AM - 12:00 PM Room L (Zoom room 12)

Chair: Shuhei Nogami (Tohoku Univ.)

10:55 AM - 11:10 AM

[2L06] Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts

(6)Development of Al-added high-Mn ODS austenitic steel for liquid metal environment

*Ryuta Kasada¹, Haoran Wang¹, Jiarui Liu¹, Hao Yu¹, Sosuke Kondo¹, Yasuki Okuno¹, Nariaki Okubo², Toko Tokunaga³, Naoko Oono⁴ (1. Tohoku Univ., 2. JAEA, 3. Aomori QSC, 4. Hokkaido Univ.)

11:10 AM - 11:25 AM

[2L07] Irradiation hardening behavior and microstructural evolution of He-irradiated V-(4-8)Cr-(0-4)Ti alloys

*Yoshiki Kitamura¹, Syuichiro Miura¹, Kenichi Fukumoto¹, Ryoya Ishigami², Takuya Nagasaka³ (1. Univ. of Fukui, 2. WERC, 3. NIFS)

11:25 AM - 11:40 AM

[2L08] Effect of temperature history on microstructural evolution in vanadium alloy irradiated in HFIR-13J

*Shuichiro Miura¹, Ken-ichi Fukumoto¹, Kohei Umehara¹ (1. Univ. of Fukui)

11:40 AM - 11:55 AM

[2L09] Thermal stability of tungsten and SiC with or without diffusion barrier (ZrN and TiN) at 1700 °C

*Yina DU¹, Tatsuya Hinoki¹, Kanjiro Kawasaki¹, Junyeab Lee¹, Fujio Shinoda¹ (1. Graduate School of Energy Science, Kyoto University)

Time reserved for Chair (11:55 AM - 12:00 PM)

Session information