Open AccessMixed plutonium-uranium carbide fuel in fast breeder test reactor
Author(s) -
P. Rodríguez
Publication year - 1999
Publication title -
bulletin of materials science
Language(s) - Uncategorized
Resource type - Journals
SCImago Journal Rank - 0.35
H-Index - 72
eISSN - 0973-7669
pISSN - 0250-4707
DOI - 10.1007/bf02749922
Subject(s) - plutonium , breeder (animal) , mox fuel , breeder reactor , uranium , materials science , nuclear engineering , nuclear fuel , spent nuclear fuel , nuclear reprocessing , nuclear power , thorium fuel cycle , carbide , environmental science , waste management , radiochemistry , metallurgy , nuclear physics , engineering , chemistry , physics , blanket , composite material
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