2020 Fall Meeting

Presentation information

Oral presentation

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

[1E01-07] Accident Tolerant Fuel

Wed. Sep 16, 2020 10:00 AM - 12:00 PM Room E (Zoom room 5)

Chair:Kazuo Kakiuchi(JAEA)

10:30 AM - 10:45 AM

[1E03] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(1) Design cocept and initial results of basic performance tests

*Nozomu Murakami1, Masaaki Onoue1, Kentaro Tanaka1, Seiichi Watanabe2, Daiki Sato2, Yuji Okada2 (1. MHI, 2. MNF)

Keywords:Light Water Reactor, Accident Tolerant, fuel cladding, coated cladding, corrosion resistant

The development project of coated zirconium based alloy fuel cladding as an accident tolerant fuel for PWR has been launched. This report introduces design concept, project plan and schedule of coated fuel cladding. Then initial results of trial manufacturing coated cladding tube, and basic performance tests, such as integral thermal shock test simulating LOCA condition, are reported. The results suggest that coating technique enables to enhance performances in both normal operating conditions and accident conditions.