NUCLEAR REPROCESSING SOLVENT TREATMENT

Abstract: A process is disclosed for the treatment of a solvent which has been used in nuclear fuel reprocessing or uranium ore purification, the solvent comprising an organophosphate ester and a hydrocarbon diluent. The process includes distilling the solvent under reduced pressure to remove substantially all the diluent and a major proportion of the organic ester, converting organophosphate to inorganic phosphate and encapsulating the residual material.

Description: NUCLEAR REPROCESSING SOLVENT TREATMENT INTRODUCTION This invention is concerned with waste treatment and in particular the treatment of solvents used in nuclear fuel reprocessing and uranium ore purification. More particularly, the invention is concerned with the treatment of a solvent comprising an organophosphate ester and a hydrocarbon diluent. A typical such solvent is tributyl phosphate and diluents are odourless kerosene (OK), dodecane or a hydrogenated propylene tetramer (HPT). The phosphate ester is typically present in an amount of between 5 and 35% by volume. PRIOR ART EP 342876 discloses a process for the treatment of such a solvent in which the alkyl phosphate is reacted with hydrogen peroxide in aqueous solution added progressively at a temperature that is above ambient temperature and in the presence of a transition metal catalyst which is a chromium compound. The aqueous hydrogen peroxide phase is maintained at a pH which is mildly acidic, neutral or mildly alkaline by the controlled introduction of alkali at a rate that is sufficient to neutralise the acid released by decomposition of the alkyl phosphate, thereby significantly accelerating the rate of decomposition of the alkyl phosphate. EP 428309 discloses a process in which the alkyl phosphate is reacted with an aqueous solution of an alkaline metal hydroxide at elevated temperature and a part of the reaction product is then reacted with an aqueous solution of hydrogen peroxide in the presence of an effective amount of a transition metal catalyst. STATEMENT OF INVENTION According to the present invention there is provided a process for the treatment of a solvent which has been used in nuclear fuel reprocessing or uranium ore purification and which comprises an organophosphate ester and a hydrocarbon diluent, the process comprising distilling the solvent under reduced pressure to remove substantially all the diluent and a major proportion of the organophosphate ester, converting organophosphate to inorganic phosphate and encapsulating the residual material. The term encapsulation is used to include vitrification or alternative encapsulation methods such as location within cement. DETAILED DESCRIPTION An embodiment of a process in accordance with the present invention will now be described with reference to the accompanying drawing which is a flow chart showing processes for the treatment of a solvent comprising tributyl phosphate and odourless kerosene in which the amount of tributyl phosphate is about 30% by volume. The first stage in the process is the distillation, under reduced pressure, of solvent which has become too degraded for further use. The distillation is carried out to remove substantially all the diluent and a major proportion of the phosphate ester, for example, 90% of the total volume of organic material. This distillate is returned to the reprocessing or ore purification process. The residual volume consists essentially of organophosphate plus some phosphatic and diluent degradation products. This material is treated to convert the organophosphate to inorganic phosphate salts, such as a calcium salt. Preferred processes are reasonably high temperature processes or chemical oxidation processes. A high temperature process may be carried out by mixing the residue solvent with a metal salt hydroxide in aqueous solution or susponsun, for instance, calcium hydroxide, and then feeding the mixture to a stirred pebble ball reactor at about 550°C, thereby producing a metal phosphate ash. This ash may be fed to vitrification plant, and the organics volatilised from the reactor and combusted. An alternative process is chemical oxidation, typically using a metallic catalyst such as sodium dichromate and hydrogen peroxide at a temperature of between ambient and boiling point (around 100°C) in an aqueous medium. This reaction produces an aqueous phosphoric acid, which is then reacted with an aqueous solution or suspension of a metal hydroxide such as calcium hydroxide. A metal phosphate salt solution is produced which is fed to vitrification or an alternative encapsulation method, such as encapsulation in cement. Prior to encapsulation, the material may be mixed with other radioactive waste. A process in accordance with the present invention is applicable to the treatment of a variety of solvents comprising an organophosphate ester and a hydrocarbon diluent. Mention has been made above to a number of hydrocarbon diluents. Two further examples of such diluents are Exxsol D80 and Isopar L. Exxsol D80 is a kerosene type material which can be used as a direct replacement for OK in reprocessing plants and has a narrower boiling point (202°-240°C) than OK (180°-280°C). Isopar L is a highly branched chain material with a very narrow boiling point range (190°-210°C).

Claims: CLAIMS 1. A process for the treatment of a solvent which has been used in nuclear fuel reprocessing or uranium ore purification and which comprises an organophosphate ester and a hydrocarbon diluent, the process comprising distilling the solvent under reduced pressure to remove substantially all the diluent and a major proportion of the organophosphate ester, converting organophosphate to inorganic phosphate and encapsulating the residual material. 2. A process according to Claim 1 in which the distillate, containing substantially all of the diluent and a major proportion of the phosphate ester, is returned to the reprocessing or purification process. 3. A process according to Claim 1 or Claim 2 in which the encapsulation process is vitrification. 4. A process according any of the preceding claims in which the organophosphate is converted to inorganic phosphate by a high temperature process or a chemical oxidation process. 5. A process according to Claim 4 in which the high temperature process comprises mixing the residual material with a metal salt hydroxide in aqueous solution and then treating the resultant material to produce a metal phosphate ash. 6. A process according to Claim 5 in which the chemical oxidation process includes using a metallic catalyst and hydrogen peroxide. 7. A process according to Claim 6 in which the chemical oxidation process is carried out at a temperature between ambient and boiling point in an aqueous medium. 8. A process according to any of the preceding claims in which the hydrocarbon diluent is odourless kerosene or a dodecane.

Inventors: EAVES CHRIS, HUTSON VICTOR GRAHAM, EAVES, CHRIS, HUTSON, VICTOR, GRAHAM
Applicants: BRITISH NUCLEAR FUELS PLC, EAVES CHRIS, HUTSON VICTOR GRAHAM, EAVES, CHRIS, HUTSON, VICTOR, GRAHAM
Application year: 1997
Main classification: G21F9
IPC codes: G21F9