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Status and first results of the CLADS-MADE-02 BWR control blade degradation test under steam-rich conditions related to 1F Unit 3 accident

Pshenichnikov, A. ; 山崎 宰春; 永江 勇二; 倉田 正輝

Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki

Preliminary results on the CLADS-MADE-02 control blade degradation test related to the problem of 1F Unit 3 accident under sufficient steam conditions will be discussed. Control blade debris distribution obtained in oxidative environment, possibility of B$$_{4}$$C interaction with hot steam, consequences of its reaction with surrounding stainless steel and Zircaloy are very important for 1F decommissioning. Experimental information with in situ video of an melt progression will be presented at the 25th international QUENCH workshop famous for attracting experts dealing with nuclear safety.

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