Patent Number: 054897378
Section: claims

1. A processing system for handling radioactive waste after a part or all of a waste slurry, which is comprised of an aqueous slurry of used ion exchange resin generated from nuclear facilities and which is stored in storage tanks, is withdrawn to an adjusting tank and after radioactive concentration of respective nuclides in the waste slurry is measured, which comprises at least one of the following steps: 1) returning the waste slurry to the storage tank without introducing the slurry into a solidifying processing system when the waste slurry is determined to be improper for processing directly, based on the measured radioactive concentration;  2) subjecting the waste slurry to an incineration process when the waste slurry is determined, based on the measured radioactive concentration, to be proper for processing by incineration, and subsequently solidifying residual material remaining from the incineration process by a solidifying process;  3) treating the waste slurry by a thermal decomposition process for removing functional groups and radioactive nuclides when the waste slurry is determined, based on the measured radioactive concentration, to be proper for further processing, and subsequently solidifying residual material obtained from the thermal decomposition process by a solidifying process;  4) subjecting the waste slurry to a dissolution process by removing radioactive nuclides when the waste slurry is determined to be proper for processing to reduce its radioactivity, based on the measured radioactive concentration, and subsequently solidifying the processed waste slurry by a solidifying process;  5) introducing the waste slurry into a solidifying process wherein the waste slurry is solidified with inorganic solidifying materials or organic solidifying materials when the waste slurry is determined to be proper for processing directly, based on the measured radioactive concentration;  6) incinerating the waste slurry when the waste slurry is determined, based on the measured radioactive concentration, to be proper for processing directly, and introducing the gaseous waste generated from the incineration of the waste slurry into a gaseous waste treatment process; or  7) diluting the waste slurry with other waste having low radioactivity when the waste slurry is determined, based on the measured radioactive concentration, to be proper for processing after reducing its level of radioactivity by dilution, so that the radioactivity of a solidified waste body obtained by a subsequent solidifying process exhibits a value within a predetermined limit which is defined as an allowable value for handling of such radioactive waste.  said measurement of radioactive concentration of respective nuclides is performed on at least either of Co-60 and Cs-137, and,  when an observed value obtained by said measurement exceeds a predetermined value, said waste is returned to the storage tank without performing the measurement of radioactive concentration on another nuclide.  said measurement of radioactive concentration of respective nuclides is performed on at least either of Co-60 and Cs-137, and  when radioactivities of nuclides other than Co-60 and Cs-137, which are estimated by a scaling factor method for estimating radioactivity of a nuclide based on observed radioactivity of the at least either of Co-60 and Cs-137 with a preferable safety factor, do not exceed predetermined values, transferring said waste to a next processing system with measurement of radioactivity on only either of Co-60 and Cs-137.  observed values in said measurement of radioactivity are recorded as data, and  said data are stored corresponding to data on radioactivity of each package obtained by the solidifying process. 2. A processing system for radioactive waste as claimed in claim 1, wherein said measurement of radioactive concentration of respective nuclides is performed qualitatively and quantitatively by using chemical analysis technique. 3. A processing system for radioactive waste as claimed in claim 1, wherein said measurement of radioactive concentration of respective nuclides is performed, in aspect of the processing applicability evaluation, on at least one of; Co-60, Cs-137, Tc-99, Ni-59, Ni-63, Sr-90, I-129, Nb-94, C-14, H-3, and transuranium elements. 4. A processing system for radioactive waste as claimed in claim 3, wherein said measurement of radioactive concentration of respective nuclides is performed additionally on gamma ray nuclides in aspect of evaluation on compliance with transportation standard after the solidification. 5. A processing system for radioactive waste as claimed in claim 1, wherein 6. A processing system for radioactive waste as claimed in claim 14, wherein 7. A processing system for radioactive waste as claimed in claim 14, wherein 8. A processing system for radioactive waste as claimed in claim 14, wherein measurement of radioactivity is performed on said waste before a solidifying process and after a solidifying process. 9. A processing system for radioactive waste as claimed in claim 8, wherein measurement of radioactivity on said waste before solidifying process is performed by sampling of said waste directly from the adjusting tank or through a sampling port furnished to the adjusting tank. 10. A processing system for radioactive waste as claimed in claim 8, wherein at least a measuring point for the measurement of radioactivity on said waste is provided in the system. 11. A processing system for radioactive waste as claimed in claim 14, wherein measurement of radioactivity is performed before and after a solidifying process, and the waste includes condensed waste liquid, incinerated ashes, and non-burnable miscellaneous solid bodies.