2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2I08-17] SiC

Thu. Sep 14, 2017 2:45 PM - 5:25 PM Room I (C310 - C Block)

Chair:Hirotatsu Kishimoto (Muroran Inst. of Tech.)

4:15 PM - 4:30 PM

[2I14] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(3)Study on fuel behavior during design base accident

*Seiichi Watanabe1, Hideyuki Teshima1, Kenichiro Furumoto1, Masaaki Katayama2, Shinichiro Yamashita3 (1. MNF, 2. MHI, 3. JAEA)

Keywords:Accident tolerant fuel, SiC composite material, Fuel cladding, PWR, Design base accident

The accident tolerant fuel with SiC fuel cladding is expected as a concept to improve safety against severe accident in light water reactors because of low reactivity with steam and high mechanical strength at elevated temperature. Several experiments and analyses simulating severe accident conditions have been performed so far. However, few experiments and analyses simulating fuel cladding behaviors under design basis accident (DBA) conditions, as typified by Loss Of Coolant Accident (LOCA), and Reactivity Initiated Accident (RIA) conditions. In this work, we developed a test apparatus to investigate the behavior of SiC under DBA conditions, and performed a mock-up test with SiC composite tube samples to confirm its capability. In the future, we will determine test conditions in detail, and obtain experimental data of SiC under DBA conditions for LOCA analysis.