Intermediate-level waste international

As part of this study, proposed radioactive waste classification systems that differ from the existing classification system in the United States were reviewed and evaluated. Of particular interest is the classification system currently recommended by the International Atomic Energy Agency (IAEA). This classification system and the disposal options for each waste class are summarized in Table 1.2. The basic waste classification system consists of exempt waste, low-and intermediate-level waste, and high-level waste. 

Lifanov, F. A., Kobelev, A. P. etal. 1998. Incorporation of intermediate-level liquid radioactive nuclear power plant wastes in glass and ceramics. Proceedings of the IT3 International Conference On Incineration and Thermal Treatment Technologies. Salt Lake City, 609-612. 

Sobolev, I. A., Dmitriev, S. A. et al. 1995a. Vitrification of intermediate level radioactive waste by induction heating. In Slate, S., Feizollahi, F. Creer, J. (eds) Proceedings of the Fifth International Conference on Radioactive Waste Management and Environmental Restoration ICEM 95, Berlin, Germany. The American Society of Mechanical Engineers, New York, 1, 1125-1127. 

IAEA, International Atomic Energy Agency, Immobilization of Low and Intermediate Level Radioactive Wastes with Polymers, Technical Reports Series No. 289, Vienna (1988)... 

Advanced technologies for the treatment of low and intermediate level radioactive wastes, IAEA Technical Report, Series No. 370, International Atomic Energy Agency, Vienna, Austria, 1994. 

Bahr, W., et al. Experiences in the Treatment of Low- and Intermediate-Level Radioactive Wastes in the Nuclear Research Center, Karlsruhe, Management of Low- and Intermediate-Level Radioactive Wastes, International Atomic Energy Agency, Vienna, 1970. Bell, M. J. The ORNL Isotope Generation and Depletion Code (ORIGEN), Report ORNL-4628, May 1973. 

IAEA, International Atomic Energy Agency, Immobilization of Low and Intermediate Level Radioactive Wastes with Polymers, Technical Reports Series No. 289, Vienna (1988) lAPWS, Guideline on the Henry s Constant and Vapor-Liquid Distribution Constant for Gases in H2O and D2O at High Temperatures, The International Association for the Properties of Water and Steam, Kyoto, Japan (2004)... 

Liquid wastes which are below exempt level and the effluents generated during treatment of short lived, low intermediate level liquid waste, containing radionuclides below safe levels are normally discharged into water bodies. TTie safe levels are site specific and are to be in conformity with international recommendations [13] [14]. The release of radioactivity is kept to the minimum... 

INTERNATIONAL ATOMIC ENERGY AGENCY, Techniques and Practices for Pretreatment of Low and Intermediate Level Solid and Liquid Radioactive Wastes, IAEA-Technical Reports Series No.272, Vienna (1987). 

INTERNATIONAL ATOMIC ENERGY AGENCY, Containers for Packaging of Solid and Intermediate Level Radio-active Wastes,IAEA-Technical Reports Series No.355, Vienna (1993). 

In general there is international agreement on what issues that are in ortant safety factors in radioaaive waste management disposal E q)erience in radioactive waste management, mainly related to low- and intermediate level radioactive waste, exist in many countries. Can we learn from this experience how regulatory requirements may be formulated What role could safety assessments have in the formulation of regulatory requirements These issues and related issues are discussed in the ptq>er. 

INTERNATIONAL ATOMIC ENERGY AGENCY. Treatment of Low- and Intermediate-Level Solid Radioactive Wastes, Technical Reports Series No. 223, IAEA, Vienna (1983). 

INTERNATIONAL ATOMIC ENERGY AGENCY, Predisposal Management of Low and Intermediate Level Radioactive Waste, IAEA Safety Standards Series No. WS-G-2.5, IAEA, Vienna (2003). 

I. Advances in Technologies for the Treatment of Low and Intermediate Level Radioactive Liquid Wastes, IAEA Technical Report Series No. 370 International Atomic Energy Agency Vienna, Austria, 1994. 

Ward D., Bryan C., and Siegel M. D. (1994) Detailed characterization and preliminary adsorption model for materials for an intermediate-scale reactive transport experiment. In Proceedings of 1994 International Conference of High Level Radioactive Waste Management, pp. 2048-2062. 

Depending on radioactivity levels the disintegrated internals will be transported either in core material transport casks to CLAB for intermediate storage or transferred to shielded waste transportation containers for final disposal in SFR (Final repository for operational and decommissioning waste). 

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