2018 Annual Meeting

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Oral presentation

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

[3D01-05] MOX Fuels for Fast Reactor

Wed. Mar 28, 2018 9:30 AM - 10:55 AM Room D (R1-212 -R1 Building)

Chair: Shuhei Miwa (JAEA)

10:15 AM - 10:30 AM

[3D04] Irradiation Behavior of Fast Reactor Fuel Pins

(1)Evaluation of Cesium Behavior by Coupled Computer Code System

*Tomoyuki Uwaba1, Keisuke Yokoyama1, Yoshihisa Ikusawa1, Junich Nemoto1, Ikuo Ishitani1, Masahiro Ito1 (1. Japan Atomic Energy Agency)

Keywords:fast reactor, MOX fuel pin, cesium, cesium uranate, fuel-cladding mechanical interaction, coupling of computer codes

Evaluation was made for Cs axial migration and FCMI due to Cs-U-O compounds in a fast reactor MOX fuel pin by coupling a computer code specialized in the Cs behavior analysis with one for analyzing overall fuel pin irradiation performance.