2016 Annual Meeting

Presentation information

Oral Presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2. Nuclear Fuel and the Irradiation Behavior

[2G01-06] Fuel behaviour evaluation

Sun. Mar 27, 2016 10:20 AM - 12:00 PM Room G (Lecture Rooms B B203)

Chair: Kosuke Tanaka (JAEA)

11:20 AM - 11:35 AM

[2G05] Development of core degradation and relocation test equipment under severe accident

*Kinya Nakamura1, Takanari Ogata1, Masaki Kurata2 (1.CRIEPI, 2.JAEA)

Keywords:fuel rod, control rod, fuel degradation, severe accident, Zircaloy oxydation

To elucidate process of fuel degradation and liquefaction in high temperature steam atmosphere condition under severe accident, fuel degradation and relocation test equipment has been developed. Preliminary experimental results used simulant fuel rods showed potential performance, such as achievement over 1500 degree C at the Zircaloy cladding surface, continuous monitoring of generated hydrogen gas and video recording of the fuel rods.