To oxidize salt waste without using reagent.
To process salt waste containing fission products generated in electrolysis purification of spent nuclear fuel using molten salt of chloride, the fission products are converted to oxide by having the salt waste and steam react in the temperature over the melting temperature of the salt waste. After recovering the oxide converted from fission products together with salt waste, it is desirable that the oxide containing salt waste and steam are made repeatedly react in the temperature over the melting temperature of the salt waste, which is desired to be 800 to 1000°C. The salt waste processing device is provided with a reaction vessel containing salt waste including fission products generated in electrolysis purification of spent nuclear fuel using molten salt of chloride, a reactor having a heater heating the reaction vessel to the temperature over the melting temperature of the salt waste and a steam supplier supplying steam to the reaction vessel.
ONOE TAKESHI
OTA KAZUAKI
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