摘要:
Disclosed are a czochralski apparatus for growing crystals and a purification method of waste salts using the same. More particularly, the present invention provides a czochralski apparatus for growing crystals comprising screw thread for fixing salt crystals mounted on a pulling bar of the apparatus in order to prevent desorption of crystals caused by load thereof during a crystal growing process without requiring alternative seed crystals and, in addition, a method for purification of waste salts, which can isolate impurities from molten waste salts using a czochralski crystal growing process without alternative adsorption medium, does not generate secondary wastes and may continuously purify the waste salts.
摘要:
Disclosed herein is a method of preparing uranium metal by electrorefining uranium metal, comprising: applying a predetermined current to an anode electrode included in an anode basket receiving fuel segments made of uranium metal and a cathode electrode of carbon material; electrodepositing uranium on the cathode electrode in accordance with the reaction initiated by the applied current; and collecting the electrodeposited uranium by self-weight. An apparatus for electrorefining uranium metal used in the method according to the present invention, comprises: an anode basket (6) receiving fuel segments made of uranium metal and comprising an anode electrode; and a reactor including a cathode electrode (5) made of carbon material and a uranium collector (10) therein. According to the method of the present invention having the above mentioned constitution and the apparatus thereof, it is possible to separate only pure uranium metal with a high capability from the spent metal nuclear fuels conveniently and economically.
摘要:
Disclosed is a structural alloy with oxidation resistance for electrolytic reduction equipment for treatment of spent nuclear fuel. More particularly, the present invention relates to a structural alloy with oxidation resistance for electrolytic reduction equipment for treatment of spent nuclear fuel wherein Cr, Si, Al, Nb and Ti are added to a Ni-based substrate so as to form an oxide coating film which is stable in a LiCl—Li2O molten salt and, in addition, a process thereof and use of the same.