Acceleration irradiation test of first-loading fuel of High Temperature Engineering Test Reactor (HTTR) up to high burnup (Joint research)

Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Takahashi, Masashi; Tobita, Tsutomu*; Hayashi, Kimio; Saito, Takashi; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Kato, Shigeru*

JAERI-Research 2002-012, 39 Pages, 2002/06

JAERI-Research-2002-012.pdf:3.12MB

no abstracts in English

Thermal fatigue testing of low-z coatings on molybdenum and inconel 625

; ; ; Murakami, Yoshio

Journal of Nuclear Materials, 111-112, p.856 - 860, 1982/00

https://doi.org/10.1016/0022-3115(82)90320-8

no abstracts in English

Development of low-z surface coatings for JT-60 first wall

Murakami, Yoshio; ; Nakamura, H.

Journal of Nuclear Materials, 111-112, p.861 - 863, 1982/00

https://doi.org/10.1016/0022-3115(82)90321-X

no abstracts in English

Study on coating technic to enhance accident tolerance of fuel cladding II, 4; Steam oxidation of Ti-coated SiC as accident tolerant fuel cladding

Pham, V. H.; Ishibashi, Ryo*; Sasaki, Masana*; Nemoto, Yoshiyuki; Yamashita, Shinichiro

no journal, , 

Silicon carbide is the most prominent candidate for accident tolerant fuel cladding in terms of oxidation resistance and cladding integrity at high temperatures in steam. However, dilution of silica from SiC in aqueous environment under long-term corrosion can become a concern when considering SiC as nuclear graded materials. In order to improve its corrosion resistance in water for normal operations, coating of Ti layer on SiC was proposed. In this study, oxidation behavior and oxidation kinetics of Ti-coated SiC are studied via a thermogravimetric system at 1200-1500C. Influence of the Ti coating layer on oxidation kinetics and behavior of SiC will then be discussed and reported.