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)

11:40 AM - 11:55 AM

[3C09] Study on coating technic to enhance accident tolerance of fuel cladding

(4) Oxidation behavior of the TiN/TiAlN multilayer coated Zry4

*Hai Pham1, Yoshiyuki Nemoto1, Shinichiro Yamashita1 (1. JAEA)

Keywords:ATF, Multilayer coating Zry, Steam oxidation

As part of an effort to improve accident resistance, a multilayer coating of TiN/TiAlN was applied to the surface of zirconium plate. In this study, oxidation tests were conducted on these specimens in high-temperature steam, and cross-sectional observations were made after the tests. In the lecture, we will introduce the results of these experiments as well as other coating technologies that we plan to develop.