2018 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2D05-09] Accident-tolerant Fuel 2

Thu. Sep 6, 2018 10:35 AM - 12:00 PM Room D (A32 -A Building)

Chair:Kan Sakamoto(NFD)

11:20 AM - 11:35 AM

[2D08] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(3) Plant transient analysis with SiC clad fuel for RIA accident

*Hideki Horie1, Yutaka Takeuchi1, Kazuo Kakiuchi1, Hisaki Sato1, Noriko Shirasu2, Hiroaki Saito2, Shinichiro Yamashita2, Tokio Fukahori2 (1. Toshiba Energy Systems & Solutions Corporation, 2. Japan Atomic Energy Agency)

Keywords:Accident Tolerant Fuel, SiC, RIA, TRAC, FEMAXI

Thermal-hydraulic and mechanical behavior of fuel using SiC cladding was evaluated for reactivity-initiated accident (RIA), and the result was compared to a behavior for fuel using Zry cladding. As a result, it was confirmed that there is not so large difference between both in the thermal-hydraulic behavior. On the other hand, it was confirmed that the mechanical behaviro depended on design conditions such as a gap width.