[2L01-04] Tritium Process

[2L02] Study of WDS for DEMO applied with heavy water cooled blanket

*Takahiko Sugiyama¹ (1. Nagoya University)

Keywords:DEMO, WDS, heavy water cooled blanket, water distillation under reduced pressure, tritium

For the fuel cycle of a DEMO fusion reactor, a key issue is removal of hydrogen while separation of tritium and deuterium is not necessary important. In order to reduce contamination by hydrogen, heavy water cooled blanket and water detritiation system were studied. Water distillation under reduced pressure was applied for isotope separation, and its operating conditions were set as 60 degrees C, 0.2 atm. Throughput, tritium concentration of the heavy water coolant, and removal rate of tritium were 6 t/h, 370 GBq/kg, and 130 g/day, respectively. Height of the distillation column was varied with cut ratio. When the cut ratio was 10^-5, the height of the column was required about 160 m.