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Characterization and Control of Solidified Radioactive Wastes According to the Italian Rules: Organization of a Characterization Facility and First Results Pages: 10 Published: Jan 1989
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View License Agreement Source: STP1033-EB Abstract According to Technical Guide No. 26, officially published in 1987 by the Italian Regulatory Body (ENEA-DISP), the radioactive wastes are now classified in Italy in accordance with the identities and the concentrations of radionuclides, no distinction being made from the point of view of the physical state. Three “radwaste” categories have been established: The first refers to wastes that decay below exemption limits for free discharge, as defined by current Italian laws, within a few months or within a few years, maximum. The second category of radwastes, which is the most important in terms of overall production, refers to those wastes whose radioactivity decays to radioactive levels comparable with the exemption limits set up for natural radioactive solids within a few centuries, maximum. The radwastes falling into this second category, which are generated mainly by nuclear power plants, must be solidified by means of suitable solidification agents such as cement, bitumen, or polymers. Moreover, a test program must be performed to assure the compliance of the waste forms with a set of specified waste form characteristics. The third category of radwastes refers to the high-activity liquids arising from the first cycle of the fuel reprocessing facilities and to the alpha-bearing wastes. The tests to be applied for the characteristics control of real radioactive solidified wastes of the second category are briefly described. They require, in some cases, that a noncommercial apparatus be operated in radiation-controlled areas. A glove-box chain, also suitable for the characterization of solidified alpha wastes, has been designed and built. The first characterization test campaign has been carried out on radwastes produced by boiling water reactor power plants solidified in cement and the results are presented. Keywords: conditioned radwastes characterization, quality assurance, boiling water reactor radwastes, ISO long-term leaching test, cesium leachability in cement, strontium leachability in cement, cobalt leachability in cement Paper ID: STP22872S Committee/Subcommittee: D34.01 DOI: 10.1520/STP22872S ASTM International is a member of CrossRef. | ||