Heterogeneity of BWR control blade degradation under steam-starved conditions

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

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

This paper presents recent results on high-temperature control blade degradation at the very beginning phase of a severe accident in BWRs. The large-scale experiment has been performed in JAEA-CLADS laboratory using Large-scale Equipment for Investigation of Severe Accidents in Nuclear reactors (LEISAN). A prototypic sequence of Fukushima Daiichi (1F) Unit 2 has been taken. It has been shown that due to specific conditions happened at Unit 2 the lack of available oxygen allowed metallic melt more flexibility for relocation and inhomogeneous redistribution of melt components due to specially recreated temperature gradient. Phase composition of remained BC control blade claddings at different elevations, and phase composition of melt has been investigated by complementary methods and have shown significant difference in elevations together with stratification of metallic components with origination of high melting point layers due to redistribution of steel components and involvement of B and C. It allowed absorber blade residuals with BC inside being severely damaged by melting to survive at 1475C and protect BC from direct contact with steam.