Recovery of Tritium from Wastewater Generated by Decommissioning of Gas Cooled Reactors (GCR)

The recovery of tritium from wastewater generated by the decommissioning of a 166-MWe GCR, Tokai-1, nuclear reactor was evaluated. The dimensions of two tritium separation columns, water distillation process and hydrogen-isotope exchange with hydrophobic Pt-catalyst, were evaluated numerically under the assumptions that the recovery of tritium from the wastewater would be completed in five years and the wastewater after the recovery of tritium would be suitable for release into the environment. It was found that, in addition to lower steam, the column was smaller than that for the water distillation process. The hydrogen-isotope exchange process was suitable for the treatment of wastewater, not only for a process design point of view but also for a reduction of energy consumption.