2022 Fall Meeting

Presentation information

Oral presentation

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

[2E09-12] Cladding Materials

Thu. Sep 8, 2022 2:45 PM - 3:55 PM Room E (E1 Bildg.2F No.24)

Chair:Hiroaki ABE(UTokyo)

3:30 PM - 3:45 PM

[2E12] Ballooning and burst behavior of pre-hydrided Zirconium alloy fuel cladding tube during loss of coolant accident at spent fuel pool

*Kinya Nakamura1, Kenta Inagaki1, Atsushi Ui1 (1. CRIEPI)

Keywords:spent fuel pool, loss-of-coolant accident, zirconium alloy, fuel cladding, burst

Balloon and burst tests of pre-hydridd zrconum alloy fuel cladding tube were conducted in a steam-air mixed or an air atmosphere to develop burst model under loss-of-coolant accident at spent fuel pools. The correlation between the pre-hydrogen concentration in the cladding tube and the burst behavior, and the effect of the ZrN crystal grains formed at the inerface of the ZrO2 / Zr substrate on the burst behavior are reported.