2023 Fall Meeting

Presentation information

Oral presentation

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

[2C21-23] Excore Corrosion Behavior, Irradiation Behavior

Thu. Sep 7, 2023 5:40 PM - 6:30 PM Room C (IB Bildg.1F IB015)

Chair:Shun Hirooka(JAEA)

5:55 PM - 6:10 PM

[2C22] Development of science-based MOX property model for irradiation behavior analysis code

*Takumi Oki1, Masato Kato1, Yoshihisa Ikusawa1 (1. JAEA)

Keywords:fast reacror, MOX, thermal conductivity, irradiation behavior

JAEA has been developing a MOX(Mixed Oxide) fuel irradiation behavior analysis code based on a scientific fuel property model for the development of future fast reactor fuels. In this study, we investigated a MOX thermal conductivity model incorporating the dependence of the Bredig transition on plutonium and minor actinide content, and evaluated the results of post-irradiation examinations of MOX fuel irradiated in JOYO using the irradiation behavior analysis code. By using this thermal conductivity to evaluate irradiation behavior, it was confirmed that not only the fuel center temperature from low temperature to just below the melting point, but also the fuel restructuring reproduced the measured values.

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