2024 Annual Meeting

Presentation 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)

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)

Keywords:Accident tolerant fuel , Cr-coated, Ion-irradiation, interface, hardening

As a candidate for accident tolerant fuel (ATF) cladding tubes, chromium (Cr) coated Zry cladding is being developed. In this study, the ion irradiation tests were conducted to investigate the effect of irradiation on Cr layer and interface between Cr layer and Zry substrate. The presentation will discuss the results of these experiments.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password