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Report No.
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R&D of the next generation safety analysis methods for fast reactors with new computational science and technology, 8; Status of R&D in FY2006

Koshizuka, Seiichi*; Liu, J.*; Morita, Koji*; Arima, Tatsumi*; Zhang, S.*; Tobita, Yoshiharu; Yamano, Hidemasa   ; Ito, Takahiro*; Naito, Masanori*; Shirakawa, Noriyuki*; Hosoda, Seigo*; Uehara, Yasushi*; Yamamoto, Yuichi*; Kozakai, Hiroshi*; Himi, Masashi*; Hirano, Etsujo*; Shimizu, Sensuke*; Oue, Masaya*

A computer code is developed based on a particle method technology in order to simulate in detail various phenomana in core disruptive accidents in fast reactors. This report is a summary of progress during FY2006 in a five-year project of the code development.

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