2020 Annual Meeting

Presentation information

Print

Oral presentation

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

[2M04-07] Zirconium

Tue. Mar 17, 2020 10:50 AM - 12:00 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Hideo Watanabe(Kyushu Univ.)

11:20 AM - 11:35 AM

[2M06] Fuel cladding deformation behavior during anticipated loss of coolant accident at spent fuel pool

(1)As-received Zircaloy-4 cladding tube

*Kinya Nakamura1, Kenta Inagaki1, Takeshi Sonoda1, Satoshi Nishimura1 (1. CRIEPI)

Keywords:spent fuel pool, loss of coolant accident, burst, fuel cladding tube, Zircaloy-4

Burst tests of as-received Zircaloy-4 cladding tube were conducted under a wide range of postulated loss-of-coolant accident (LOCA) conditions at spent fuel pool (SFP) to develop a cladding deformation model leading to burst based on a realistic SFP-LOCA scenario. As a result, it was suggested that the effect of the air ratio in the atmosphere on the burst temperature is negligible.