First analyses of concrete-corium solids surrogate for the Fukushima Daiichi severe accidents

福島第一原子力発電所条件を考慮した溶融バーコンクリート反応生成物の分析

Brissonneau, L.*; Gousseau, J.*; Piluso, P.*; Bouyer, V.*; 北垣 徹  ; 池内 宏知  ; 矢野 公彦 ; 鷲谷 忠博 

Brissonneau, L.*; Gousseau, J.*; Piluso, P.*; Bouyer, V.*; Kitagaki, Toru; Ikeuchi, Hirotomo; Yano, Kimihiko; Washiya, Tadahiro

In case of severe accident in a nuclear reactor, the mixture obtained from fuel core and pins (mainly UO and zirconium), called corium, can penetrate the steel vessel and interact with the concrete, as in the Fukushima Daiichi NPP (1F) severe accidents. A specific test has been realized with a concrete similar to the one of the Fukushima Daiichi NPP (1F) and an "oxide metal" corium. Ten samples were collected from representative places (corium core, crust, vertical and horizontal interfaces) and examined by SEM and XRD. The talk will present some of the main features of the solids formed after CCI.