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Journal Articles

OCCD/NEA Specialist Mtg. on Fuel-Coolant Interactions

Akiyama, Mamoru*; Yamano, Norihiro

Nihon Genshiryoku Gakkai-Shi, 35(7), p.630 - 631, 1993/07

no abstracts in English

Oral presentation

Development of visualization technique for penetration behavior of simulant melt in sodium

Emura, Yuki; Kamiyama, Kenji; Matsuba, Kenichi; Isozaki, Mikio

no journal, , 

In case of core disruptive accident in sodium-cooled fast reactors, it is thought that molten-core material will be discharged into the lower plenum and fragmented there due to fuel-coolant interactions. To understand this fragmentation behavior, we performed the simulation test in which molten stainless steel discharged into sodium pool and fragmentation behavior was observed using a visualization system combined X-ray and high-speed camera. Both successful visualization of fragmentation behavior by above visualization system and rapid cooling of molten stainless steel due to fragmentation are presented in this study.

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