TY - JOUR
T1 - Conceptual design of a breeding blanket with super-heated steam cycle for CREST-1
AU - Asaoka, Yoshiyuki
AU - Okano, Kunihiko
AU - Yoshida, Tomoaki
AU - Tomabechi, Ken
AU - Ogawa, Yuichi
AU - Sekimura, Naoto
AU - Fukai, Yuzo
AU - Hatayama, Akiyoshi
AU - Inoue, Nobuyuki
AU - Kohyama, Akira
AU - Yamazaki, Sei Ichiro
AU - Mori, Seiji
PY - 2000/9
Y1 - 2000/9
N2 - Compact REversed Shear Tokamak (CREST-1) is a conceptual design of water-cooled commercial reactor based on a reversed shear high beta equilibrium. The conceptual design of a tritium breeding blanket for CREST-1 is presented. This blanket design is based on low activation ferritic steel components and an advanced super-heated steam cycle. This design gives high thermal efficiency for the reduction of electricity cost. CREST-1 generates about 1.16 GWe electric power.
AB - Compact REversed Shear Tokamak (CREST-1) is a conceptual design of water-cooled commercial reactor based on a reversed shear high beta equilibrium. The conceptual design of a tritium breeding blanket for CREST-1 is presented. This blanket design is based on low activation ferritic steel components and an advanced super-heated steam cycle. This design gives high thermal efficiency for the reduction of electricity cost. CREST-1 generates about 1.16 GWe electric power.
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U2 - 10.1016/S0920-3796(00)00149-6
DO - 10.1016/S0920-3796(00)00149-6
M3 - Article
AN - SCOPUS:0034259076
SN - 0920-3796
VL - 48
SP - 397
EP - 405
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 3
ER -