TY - JOUR
T1 - Key aspects of the safety study of a water-cooled fusion DEMO reactor
AU - Nakamura, Makoto
AU - Tobita, Kenji
AU - Someya, Youji
AU - Tanigawa, Hisashi
AU - Gulden, Werner
AU - Sakamoto, Yoshiteru
AU - Araki, Takao
AU - Watanabe, Kazuhito
AU - Matsumiya, Hisato
AU - Ishii, Kyoko
AU - Utoh, Hiroyasu
AU - Takase, Haruhiko
AU - Hayashi, Takumi
AU - Satou, Akira
AU - Yonomoto, Taisuke
AU - Federici, Gianfranco
AU - Okano, Kunihiko
N1 - Publisher Copyright:
© 2014 The Japan Society of Plasma Science and Nuclear Fusion Research.
PY - 2014
Y1 - 2014
N2 - Key aspects of the safety study of a water-cooled fusion DEMO reactor is reported. Safety requirements, dose target, DEMO plant model and confinement strategy of the safety study are briefly introduced. The internal hazard of a water-cooled DEMO, i.e. identification of hazardous inventories, identification of stored energies that can mobilize these hazardous inventories and identification of accident initiators and scenarios, are evaluated. It is pointed out that the enthalpy in the first wall/blanket cooling loops, the decay heat and the energy potentially released by the Be-steam chemical reaction are of special concern for the water-cooled DEMO. An ex-vessel loss-of-coolant accident (ex-VV LOCA) of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.
AB - Key aspects of the safety study of a water-cooled fusion DEMO reactor is reported. Safety requirements, dose target, DEMO plant model and confinement strategy of the safety study are briefly introduced. The internal hazard of a water-cooled DEMO, i.e. identification of hazardous inventories, identification of stored energies that can mobilize these hazardous inventories and identification of accident initiators and scenarios, are evaluated. It is pointed out that the enthalpy in the first wall/blanket cooling loops, the decay heat and the energy potentially released by the Be-steam chemical reaction are of special concern for the water-cooled DEMO. An ex-vessel loss-of-coolant accident (ex-VV LOCA) of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.
KW - Accident scenario analysis
KW - Hazard analysis
KW - Safety study
KW - Safety system
KW - Water-cooled fusion DEMO
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U2 - 10.1585/pfr.9.1405139
DO - 10.1585/pfr.9.1405139
M3 - Article
AN - SCOPUS:84988446436
SN - 1880-6821
VL - 9
JO - Plasma and Fusion Research
JF - Plasma and Fusion Research
M1 - 1405139
ER -