Speaker
Dr
Youji Someya
(Japan Atomic Energy Agency)
Description
This paper presents safety and waste management studies for a fusion DEMO reactor. It was found that an impact of a large-scale ex-vessel loss-of-coolant accident (LOCA), i.e., a guillotine rupture of a main pipe of the primary cooling system with pressurized water reactor (PWR) condition (320ºC, 16 MPa), can be mitigated by using a vault for the Tokamak Cooling Water System (TCWS) with a pressure suppression system. A management scenario of radioactive waste generated in every replacement of in-vessel components was developed in consideration of residual heat, dose rate and tritium removal. An additional important finding is that all the radwaste will be disposed of in shallow land burial after the 10 year interim storage for cooling down the radioactivity.
| Country or International Organization | Japan |
|---|---|
| Paper Number | SEE/P7-5 |
Primary author
Dr
Youji Someya
(Japan Atomic Energy Agency)
Co-authors
Akihiro Masui
(Japan Atomic Energy Agency)
Hisashi Tanigawa
(Japan Atomic Energy Agency)
Kazuhito Watanabe
(Japan Atomic Energy Agency)
Kenji Tobita
(Japan Atomic Energy Agency)
Dr
Makoto Nakamura
(Japan Atomic Energy Agency)
