2022 Annual Meeting

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Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[2J05-08] Severe Accident 3

Thu. Mar 17, 2022 2:45 PM - 4:00 PM Room J

Chair: Teppei Otsuka (Kindai Univ.)

3:00 PM - 3:15 PM

[2J06] Study on Cr coated cladding

(2)Investigation of the metallography after LOCA test

*Afiqa Mohamad1, Yuji Okada2, Daiki Sato2, Ikuo Ioka1, Eriko Suzuki1, Yoshiyuki Nemoto1 (1. JAEA, 2. MNF)

Keywords:ATF, coated Zr alloy cladding, LOCA test, high temperature

Cr-coated Zr based alloy cladding was fabricated by sputtering technique and its metallography after simulated loss-of-coolant accident (LOCA) tests at high temperature was studied in details.