Speaker
Dr
Makoto Nakamura
(Japan Atomic Energy Agency)
Description
Safety of tokamak DEMO cooled by pressurized water has been studied for the first time. We have quantitatively assessed consequences of two types of accidents: ex-vessel and in-vessel loss-of-coolant accidents (LOCAs) of the first wall/blanket cooling channels. As for the former case, we have analyzed ex-vessel double-ended break of the cooling channel. The analysis result suggests that the reactor building has a mitigation function of tritium release to the environment against the ex-vessel LOCA. As for the latter case, we have analyzed multiple, double-ended outboard first wall cooling pipe break in the vacuum vessel of the whole perimeter in the toroidal direction. The analysis result suggests that the pressure in the vacuum vessel reaches the design value even though the pressure suppression system is in operation. Possible safety provision for such a major in-vessel LOCA is proposed.
| Country or International Organisation | Japan |
|---|---|
| Paper Number | SEE/P5-10 |
Primary author
Dr
Makoto Nakamura
(Japan Atomic Energy Agency)
Co-authors
Dr
Hisashi Tanigawa
(Japan Atomic Energy Agency)
Dr
Kenji Tobita
(Japan Atomic Energy Agency)
Dr
Kenzo Ibano
(The University of Tokyo)
Dr
Werner Gulden
(Fusion for Energy)
Dr
Youji Someya
(Japan Atomic Energy Agency)
Dr
Yuichi Ogawa
(The University of Tokyo)
