2017 Fall Meeting

Presentation information

Oral presentation

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

[3J14-16] Behavior of FPs 2

Fri. Sep 15, 2017 3:50 PM - 4:40 PM Room J (C309 - C Block)

Chair:Yuji Arita (Univ. of Fukui)

4:05 PM - 4:20 PM

[3J15] Axial migration and accumulation behavior of cesium in fast reactor fuel pins

(2)Evaluation of diameter change of fuel pellet by cesium local accumulation

*Takashi Tanno1, Hiroshi Oka1, Yoshihisa Ikusawa1, Tomoyuki Uwaba1, Takeji Kaito1 (1. JAEA)

Keywords:Fast reactor, Cesium, High burn-up, FCMI, MOX, Diameter change of fuel pellet

Evaluation of diameter changes of fuel pellets by cesium (Cs) accumulation based on γ-scan profiles was carried out in order to estimate the influence of axial migration and accumulation behavior of Cs for fuel-cladding mechanical interaction (FCMI). Local diameter change and FCMI of the blanket pellets facing MOX pellets were predicted for EBR-II irradiation test.