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VITRIFICATION OF LOW AND INTERMEDIATE LEVEL WASTE: TECHNOLOGY AND GLASS PERFORMANCE

F. A. Lifanov, Igor A. Sobolev, С. А. Дмитриев, Sergey V. Stefanovsky, Michael I. Ojovan, William Lee, R. Burcl

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Abstract

Vitrification currently is being used successfully to immobilise high-level radioactive waste (HLW) from spent nuclear fuel reprocessing. Development of vitrification technologies for low and intermediate level radioactive waste (LILW) is becoming increasingly important and large programmes are initiated in a number of countries including Russia. Moscow SIA “Radon” has immobilised LILW operational waste from nuclear power plants (NPP) and institutional radioactive waste in borosilicate glass matrices since the 1970s. The current cold crucible high frequency induction melters (CCM) are used to vitrify liquid radioactive wastes collected from facilities in the central European part of Russia. Borosilicate glasses and glass composite materials immobilising LILW demonstrate reliable retention of radionuclides as confirmed by extended long-term tests in field conditions.

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What this paper is about

Vitrification currently is being used successfully to immobilise high-level radioactive waste (HLW) from spent nuclear fuel reprocessing. Development of vitrification technologies for low and intermediate level radioactive waste (LILW) is becoming increasingly important and large programmes are initiated in a number of countries including Russia. Moscow SIA “Radon” has immobilised LILW operational waste from nuclear power plants (NPP) and institutional radioactive waste in borosilicate glass matrices since the 1970s. The current cold crucible high frequency induction melters (CCM) are used to vitrify liquid radioactive wastes collected from facilities in the central European part of Russia. Borosilicate glasses and glass composite materials immobilising LILW demonstrate reliable retention of radionuclides as confirmed by extended long-term tests in field conditions.

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Available abstract

Vitrification currently is being used successfully to immobilise high-level radioactive waste (HLW) from spent nuclear fuel reprocessing. Development of vitrification technologies for low and intermediate level radioactive waste (LILW) is becoming increasingly important and large programmes are initiated in a number of countries including Russia. Moscow SIA “Radon” has immobilised LILW operational waste from nuclear power plants (NPP) and institutional radioactive waste in borosilicate glass matrices since the 1970s. The current cold crucible high frequency induction melters (CCM) are used to vitrify liquid radioactive wastes collected from facilities in the central European part of Russia. Borosilicate glasses and glass composite materials immobilising LILW demonstrate reliable retention of radionuclides as confirmed by extended long-term tests in field conditions.

Key concepts: Vitrification, Borosilicate glass, Radioactive waste, High-level waste, Waste management, Radionuclide, Crucible (geodemography), Environmental science

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VITRIFICATION OF LOW AND INTERMEDIATE LEVEL WASTE: TECHNOLOGY AND GLASS PERFORMANCE — Research Paper | ScholarLens