2022 Annual Meeting

Presentation information

Oral presentation

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

[3J01-06] SiC 1

Fri. Mar 18, 2022 9:30 AM - 11:15 AM Room J

Chair: Kenta Murakami (UTokyo)

10:30 AM - 10:45 AM

[3J05] R&D of anti-corrosion technology for full-ceramics reactor core

(5)Small specimen shear stress testing on ceramics coating

*Shaofan Lyu1, Hirokazu Katsui2, Hao Yu1, Yasuki Okuno1, Ryuta Kasada1, Sosuke Kondo1 (1. Tohoku University, 2. National Institute of Advanced Industrial Science and Technology)

Keywords:ceramics coating, shear strength, double notch test, ATF, cladding

Silicon carbide (SiC) have gained a great deal of attention as one of the next generation materials for core component in nuclear reactors due to its excellent properties in high-temperature. The corrosion of SiC is accelerated by irradiation in various coolants. To improve the corrosion resistance of SiC, the coated layer is believed to be essential. The Al2O3 is coated at SiC substrate to improve the corrosion resistance of SiC. In this study, double notched shear (DNS) testing is employed for evaluating the shear stress of each interface with two types of mullite fabricated under various conditions so as to optimize the coating system. The sample is irradiated by Silicon ion. irradiation-induced shear-stress modification is newly found.