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)

10:35 AM - 10:50 AM

[2D05] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(5) Evaluation of influence on core neutronics characteristics and fuel behavior

*Nozomu Murakami1, Kazuki Kirimura1, Kazuya Yamaji1, Daisuke Sato1, Seiichi Watanabe2, Daiki Sato2, Kenichiro Furumoto2, Shinichiro Yamashita3, Tokio Fukahori3 (1. MHI, 2. MNF, 3. JAEA)

Keywords:Light Water Reactor, Safety Improvement, Accident Tolerant, Fuel Cladding, SiC

SiC cladding characteristics and behaviors (Lower thermal conductivity of SiC cladding than that of Zr-based cladding and so on) cause fuel temperature to increase, and consequently to decrease reactor Shutdown margin (SDM). As a result of this study, smaller fuel rod diameter with hollow pellet is one of the solutions to maintain current level of SDM.