2020 Annual Meeting

Presentation information

Oral presentation

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

[2A04-07] Irradiation Behavior of Fuel Pellets and Claddings

Tue. Mar 17, 2020 10:50 AM - 11:55 AM Room A (Lecture Bildg. L 1F L-4)

Chair:Ken Kurosaki(Kyoto Univ.)

10:50 AM - 11:05 AM

[2A04] Evaluation of pore migration behavior during irradiation to affect the MA-bearing MOX fuel restructuring by 2-dimensional analyses

*Takayuki Ozawa1, Shun Hirooka1, Masato Kato1, Filippo Verdolin2, Stephen Novascone2 (1. Japan Atomic Energy Agency (JAEA), 2. Idaho National Laboratory (INL))

Keywords:MA-bearing MOX fuel, Irradiation behavior, 2-dimensional analysis

3-dimensional analysis code BISON-MOX to be applied for the irradiation behavior of MOX fuels is being developed by installing MOX fuel properties and analysis models to BISON, which has been developed in INL. Applying the thermal conductivity of MOX fuel and the pore migration model based on vapor pressure of vapor species, the O/M dependence of fuel restructuring observed in MA-bearing MOX fuels irradiation in Joyo were evaluated by 2-dimensional analyses with BISON-MOX.