Method for thermal decomposition treatment of radioactive waste

• US 4,895,678 A
• Filed: 06/08/1989
• Issued: 01/23/1990
• Est. Priority Date: 09/16/1987
• Status: Expired due to Term

• Current Assignee: Japan Nuclear Cycle Development Institute (Japan Atomic Energy Agency)
• Original Assignee: Doryokuro Kakunenryo Kaihatsu Jigyodan
• Inventors: Tamai, Hideaki, Ohuchi, Jin, Ohtsuka, Katsuyuki
• Primary Examiner(s): Locker, Howard J.
• Application Number:
  US07/363,305
• Time in Patent Office: 229 Days
• Field of Search: 252/626, 252/628, 252/632, 110/237, 110/238, 110/342, 110/345, 159/47.3, 159/DIG. 12, 241/DIG. 38, 204/1.5, 204/157.21, 204/157.4, 373/29, 373/22, 373/30, 373/33, 373/35, 373/36
• US Class Current: 588/18
• CPC Class Codes: G21F 9/14 by incineration; by calcination, e.g. desiccation
• CPC Class Codes: G21F 9/30 Processing separating different isotopes of the same chemical element B01D59/00
• CPC Class Codes: G21F 9/308 by melting the waste G21F9/305, G21F9/32 take precedence
• CPC Class Codes: Y10S 159/12 Radioactive

Abstract

A method for thermal decomposition treatment of a radioactive waste uses an apparatus comprising a container for holding molten matter of a radioactive waste containing a sodium compound, a pair of electrodes contacting the molten matter, and a power source for applying voltage between the electrodes while changing the polarity thereof every several tens of seconds. In this apparatus, the molten matter can be heated in the container by Joule heat, which is evolved by electric current directly flowed through the molten matter, so that the sodium compound contained in the radioactive waste can be decomposed, vaporized and removed to recover a stabilized radioactive solid as a residue in the container.

Claims

1. A method of thermal decomposition treatment of radioactive liquid waste containing sodium compound, which method comprises the steps of:

heating the radioactive liquid waste to evaporate a liquid component therein and to form a radioactive dried matter containing the sodium compound;

introducing the radioactive dried matter into a container which has a heating device for melting said sodium compound in said radioactive dried matter within said container, a pair of electrodes and a power source for applying voltage between said electrodes;

heating said radioactive dried matter by using said heating device to melt said sodium compound in said radioactive dried matter;

applying electric current to said electrodes while changing the polarity of the voltage every several tens of seconds to directly heat said molten sodium compound by Joule heat, thereby decomposing, vaporizing and removing said sodium compound to form a stabilized radioactive solid as a residue in the container; and

taking out said stabilized radioactive solid from said container.

2. The method according to claim 1, wherein said power source changes the polarity of the voltage to be applied once every about 30 seconds.

3. The method according to claim 1, wherein said pair of electrodes comprises two electrodes inserted in said container.

4. The method according to claim 1, wherein one of said pair of electrodes comprises said container made of an electrode material and the other of said pair of electrodes comprises an electrode inserted into the center of said container.

5. The method according to claim 1, wherein said radioactive liquid waste to be treated comprises a high-level liquid waste containing sodium nitrate.