Development of glass matrix for immobilization of Cs/Sr fraction after HLW partitioning

Conference · Sun Jul 01 00:00:00 EDT 2007

OSTI ID:20979662

Aloy, A S; Trofimenko, A V ^[1]; Glagolenko, Yu V ^[2]

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1. FSUE RPA 'V.G. Khlopin Radium Institute', 2nd Murinsky Ave., 28, St. Petersburg, 194021 (Russian Federation)
2. FSUE PA 'Mayak', Ozersk, Chelyabinsk's region (Russian Federation)

The paper describes experimental results on selection of the borosilicate glass matrices for immobilization of {sup 90}Sr/{sup 137}Cs fraction. The glass matrix compositions ranging from the following wt.%: sodium oxide (10-20), born oxide (10-17), silica (45-50), alumina (2-5), as well as the total of barium, lead, and titanium oxides (4-6) are found to assure generation of homogenous and chemically stable glasses. The melting temperature for these glass compositions does not exceed 1150 deg. C. The leach rates of the main glass components (sodium, silicon, and boron) for leaching into distilled water at the temperature range of 20-130 deg. C are within 10{sup -6}-10{sup -4} g/cm{sup 2}.day. PA 'Mayak' fabricated a high activity level glass block containing 6.9 wt.% of SrO and 13.1 wt.% Cs{sub 2}O in their hot cells. The leach rates from the block surface into water were as follows: 3.5.10{sup -6} g/cm{sup 2}.day for {sup 90}Sr and (1.0-3.0).10{sup -5} g/cm{sup 2}.day for {sup 137}Cs at SA/V {approx_equal} 0,1 cm{sup -1}. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 20979662
• Resource Relation: Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 4 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALUMINIUM OXIDES
BOROSILICATE GLASS
CESIUM 137
CESIUM OXIDES
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
MELTING POINTS
SODIUM OXIDES
STRONTIUM 90
STRONTIUM OXIDES
TEMPERATURE RANGE 0273-0400 K
TITANIUM OXIDES
VITRIFICATION