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Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Gulden, W.*; Sakamoto, Yoshiteru; Araki, Takao*; Watanabe, Kazuhito*; Matsumiya, Hisato*; Ishii, Kyoko*; et al.
Plasma and Fusion Research (Internet), 9, p.1405139_1 - 1405139_11, 2014/10
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. radioactive inventories, stored energies that can mobilize these inventories and 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 of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.
Abe, Hitoshi; Yoshida, Kazuo; Fukasawa, Tetsuo*; Muramatsu, Ken*; Ikeda, Yasuhisa*
no journal, ,
On the basis of Fukushima Dai-ichi Nuclear Power Plant accident, evaluation of risk of severe accident (SA) for nuclear fuel cycle facility and investigation of ensuring and improving of safety on the evaluation became urgent problem. In Reprocessing and Recycle Technology Division of Atomic Energy Society of Japan, procedure of selection of the SA on the scientific technological viewpoints for the nuclear fuel cycle facility has been investigated at Nuclear Fuel Cycle facility Severe Accident Working Group (SAWG). In this session, procedure of selection of the SA which should be considered, criterion for judgment for the selection and application example to evaluation of risk as the investigation results in SAWG will be presented.
