Measurement and modelling of properties of (U,Pu)O doped with simulated FP elements

模擬FP元素を添加した(U,Pu)O の物性の測定とモデリング

廣岡 瞬 ; 堀井 雄太 ; Vauchy, R.  ; 林崎 康平 ; 大和田 英明*; 古澤 尚也*; 山田 忠久*; 砂押 剛雄*; 宇野 弘樹*; 永沼 正行  ; 齋藤 浩介

Hirooka, Shun; Horii, Yuta; Vauchy, R.; Hayashizaki, Kohei; Owada, Hideaki*; Furusawa, Naoya*; Yamada, Tadahisa*; Sunaoshi, Takeo*; Uno, Hiroki*; Naganuma, Masayuki; Saito, Kosuke

Studies on modelling fuel properties as a function of burn-up are limited to thermal conductivity and still rely on the experimental data reported in the 1970s using simulated irradiated fuels doped with fission-product (FP) elements. The use of simulated irradiated fuels rather than real irradiated fuels is an efficient approach to studying the intrinsic effect of FP on the fuel properties because the other factors such as microstructural evolution and accumulation of radiation damage during irradiation also have significant influences on the properties. In this study, we fabricated simulated MOX pellets by adding soluble FP elements (Nd, Sm, Zr, Ce, Gd, La) and measured thermo-physical properties. The results of property measurement such as thermal conductivity will be presented as an ongoing project together with literature data for comparison. Also, property changes with increasing burn-up are analyzed based on the FP yields calculated by ORIGEN2.