2019 Fall Meeting

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Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2E11-18] Stainless Steel Cladding

Thu. Sep 12, 2019 2:45 PM - 4:55 PM Room E (Common Education Bildg. 2F A23)

Chair:Tatsumi Arima(Kyushu Univ.)

4:00 PM - 4:15 PM

[2E16] R&D of advanced stainless steels for BWR fuel claddings (4)

(6) High temperature water corrosion and high temperature steam oxidation properties

*Katsuhito Takahahshi1, Yusuke Miura1, Kan Sakamoto1, Shin-ichiro Yamashita2 (1. NFD, 2. JAEA)

Keywords:Light water reactor, Accident tolerance fuel, Oxide dispersion strengthen, High tempereture water corrosion, Steam oxidation

事故耐性に優れた改良ステンレス鋼燃料被覆管の研究開発を実施している。本発表では、改良ステンレス鋼燃料被覆管の高温高圧水中での腐食挙動および高温水蒸気中での酸化特性について報告する。