Claims
- 1. A method of processing radioactive organic waste occurring in a nuclear power plant for storage, comprising:
- reducing the volume of said radioactive organic waste, wherein said radioactive organic waste includes at least one of a spent ion exchange resin and spent filter assistant by converting said radioactive organic waste to inorganic waste by way of an oxidation decomposition process with liquid hydrogen peroxide, said at least one of said spent ion exchange resin and said spent filter assistant being decomposed into water and carbon dioxide by way of the oxidation decomposition process with said hydrogen peroxide liquid to leave a residue of inorganic waste;
- neutralizing the residue of the inorganic waste with an alkali substance;
- pulverizing the residue of the inorganic waste; and
- packing the pulverized inorganic waste in a container with an inorganic hardening agent to solidify the resulting mixtures therein.
- 2. A process according to claim 1, wherein 95 to 98% by weight percent of the at least one of spent ion exchange resin and spent filter assistant organic waste is converted to inorganic waste.
- 3. A process according to claim 1, wherein after pulverizing and before packing, the inorganic waste is formed into pellets.
- 4. A process according to claim 3 wherein the radioactive organic waste is spent ion exchange resin and the pellets can withstand a load of 1 kg.
- 5. A process according to claim 3 wherein the volume reduction ratio is in the range of about 1/3.9 to 1/173.
- 6. A process according to claim 3 wherein the weight reduction ratio is in the range of 1/2.2 to 1/100.
- 7. A method of processing radioactive organic waste in a slurry occurring in a nuclear power plant for storage, comprising:
- reducing the volume of said radioactive organic waste, wherein said radioactive organic waste includes at least one of a spent ion exchange resin and spent filter assistant by converting said radioactive organic waste to inorganic waste by way of an oxidation decomposition process with hydrogen peroxide liquid in the presence of one of ferric ions and chromate ions, so that said at least one of said spent ion exchange resin and said spent filter assistant is decomposed into water and carbon dioxide by way of the oxidation decomposition process with the hydrogen peroxide liquid to leave a residue of inorganic waste;
- neutralizing the residue of inorganic waste with an alkali substance;
- heating the neutralized residue of inorganic waste to concentrate the same;
- pulverizing the neutralized and concentrated residue of inorganic waste; and
- pelletizing the pulverized residue of inorganic waste.
- 8. A method according to claim 7, wherein the oxidation-decomposition occurs in the presence of a catalyst selected from the group consisting of ferric sulfate and potassium chromate.
- 9. A process according to claim 7, wherein the hardening agent is selected from the group consisting of sodium silicate, potassium silicate, calcium silicate and cement.
- 10. The process according to claim 7, wherein oxidation occurs at a temperature of 80.degree.-100.degree. C. as well as in the presence of compressed air, said compressed air being supplied constantly.
- 11. The process according to claim 10, wherein the OH radical is produced which works on cross-linked portions of the resin to convert the same into carbon, hydrogen, water and carbon dioxide.
- 12. The process according to claim 7, wherein the concentration of ferric ion is in the range of 0.02-0.06 mol/liter for waste and ion exchange resin, and in a greater range for waste cation exchange resin.
- 13. The process according to claim 7, wherein the neutralized waste is concentrated to 18 weight percent solids prior to pulverizing.
- 14. A process according to claim 7, wherein the ion exchange resin is anion exchange resin and the catalyst is potassium chromate.
- 15. A process according to claim 7, wherein the radioactive organic waste is spent ion exchange resin and the pellets can withstand a load of 1 kg.
- 16. A process according to claim 7, wherein the heated, neutralized waste is pulverized in a centrifugal film drier.
- 17. A process according to claim 7 wherein the alkali substance is a 20% solution of sodium hydroxide.
Priority Claims (1)
Number |
Date |
Country |
Kind |
57-96585 |
Jun 1982 |
JPX |
|
Parent Case Info
This application is a continuation of application Ser. No. 500,827, filed June 3, 1983, now abandoned.
US Referenced Citations (13)
Foreign Referenced Citations (6)
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Country |
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May 1979 |
DEX |
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Jan 1980 |
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May 1978 |
JPX |
0103998 |
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0103997 |
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Non-Patent Literature Citations (1)
Entry |
Hawley, G., 1981, The Condensed Chemical Dictionary, Van Nostrand Reinhold Company, New York, p. 545. |
Continuations (1)
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Number |
Date |
Country |
Parent |
500827 |
Jun 1983 |
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