Abstract
The advanced tritium extraction system (TES) and coolant purification system (CPS) is designed to directly separate hydrogen isotopes containing tritium from purge gas and coolant gas at high temperatures (773–873 K). In order to explore whether the cogeneration can be fully used for preheating at this temperature to make the hydrogen pump (HP) work normally, the electrochemical HP based on chemically-stable BaZr0.8Y0.16Ni0.04O3-δ (BZYN) protonic electrolyte and SrFe0.8Mo0.2O3-δ (SFM) symmetrical electrodes is proposed. Hydrogen was almost completely extracted from a mixed gas with 0.1% hydrogen when the voltage of only 1.50 V was applied on the protonic HP at 873 K. And hydrogen was extracted from a mixed gas with 10 vppm hydrogen when the applied voltage was about 15.16 V at 873 K. The results have suggested that the electrochemical hydrogen pump based on BZYN is promising for advanced TES and CPS in fusion reactor.
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