Session information

Oral presentation

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

[3C06-09] Cladding Coating

Thu. Mar 28, 2024 10:55 AM - 12:00 PM Room C (21Bildg.2F 21-205)

Chair:Kenta Murakami(UTokyo)

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10:55 AM - 11:10 AM

[3C06] Study on coating technic to enhance accident tolerance of fuel cladding

(1) Overview of accident tolerant coating technic studies and apparatus development in JAEA

*Shinichiro Yamashita¹, Afiqa Mohamad¹, Yoshiyuki Nemoto¹, Yasutaka Soma¹, Yasuhiro Ishijima¹, Tomonori Sato¹, Ikuo Ioka¹, Hai vu Pham¹, Shuhei Miwa¹, Kunihisa Nakajima¹ (1. Japan Atomic Energy Agency)

11:10 AM - 11:25 AM

[3C07] Study on coating technic to enhance accident tolerance of fuel cladding

(2) Oxidation and hydriding behavior of the Cr coated Zry4

*Keito Kawai¹, Yosiyuki Nemoto², Shinichiro Yamasita², Yasuhiro Ishijima², Ikuo Ioka², Koudai Funamoto³, Hisao Atsumi¹ (1. Kindai Univ., 2. JAEA, 3. Tocalo)

11:25 AM - 11:40 AM

[3C08] Study on coating technic to enhance accident tolerance of fuel cladding

(3) Irradiation behavior of the Cr coated MDA cladding

*Afiqa Mohamad¹, Chen Jiao¹, Ikuo Ioka¹, Eriko Suzuki¹, Keietsu Kondo¹, Yoshiyuki Nemoto¹, Nariaki Okubo¹, Shinichiro Yamashita¹, Yuji Okada², Daiki Sato² (1. JAEA, 2. MHI)