2021 Annual Meeting

Presentation information

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.)

Keywords:Advanced Blanket, ADS , PbBi corrosion, Reduced-activation austenitic ODS steel

The development of Fe-Mn-Cr-Al-C steels and their oxide dispersion strengthened (ODS) steels, which are reduced-activation austenitic (RAA) steels, have been newly developed for application to ADS reactor materials and advanced fusion reactor blankets. Although the compositions of the past Fe-Cr-Mn RAA steel were reviewed, our new RAA steels were designed considering the TWIP steels used for automotive steels, with the aim of improving the high-temperature strength and irradiation resistance by ODS. In this presentation, the alloy design strategy and the initial findings on the effects of ODS on material strength and lead-bismuth corrosion of the prototypes at the laboratory level are presented. Issues for application of these RAA steels to advanced fusion reactor blankets are also discussed.