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Browsing by Subject "U-233 fissile material"

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Issue Date	Title	Author(s)
Jan-2013	Comparison of (Th-U-233) O-2 and (Th-U-235) O-2 fuel burn up into a thermal research reactor using MCNPX 2.6 code	Feghhi, S.A.H.; Gholamzadeh, Z.; Soltani, L.; Tenreiro, C.

Showing results 1 to 1 of 1