Development of glasses for the vitrification of High Level Liquid Waste (HLLW) in a joule heated ceramic melter

Waste Management

Volumn 16, Issue 7, 1996, Pages 571-578

  Luckscheiter, B ^a   Nesovic, M ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

BOROSILICATE GLASS; COMPOSITION EFFECTS; DURABILITY; ELECTRIC RESISTANCE; LITHIUM; MIXTURES; SODIUM; SOLIDIFICATION; SOLUTIONS; VISCOSITY;

HIGH LEVEL LIQUID WASTE; JOULE HEATED CERAMIC MELTER;

RADIOACTIVE WASTE VITRIFICATION;

GLASS; LITHIUM; SODIUM;

ARTICLE; CHEMICAL COMPOSITION; ELECTRIC RESISTANCE; LEACHING; NUCLEAR WASTE; PRIORITY JOURNAL; VISCOSITY; WASTE MANAGEMENT;

EID: 0030433019     PISSN: 0956053X     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0956-053X(97)88231-1     Document Type: Article

References (10)

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2. 2. Schiewer, E. The borosilicate glass for PAMELA. Radioactive Waste Management and the Nuclear Fuel Cycle 7: 121 (1986).
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5. 5. Baucke, F. and Werner, R. D. Mixed alkali effect of electrical conductivity in glass-forming silicate melts. Glastechnische Berichte 62: 182 (1989).
6. 10 Poises. Technol. Rep. Kansai Univ. 14: 51 (1973).
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9. 2. J. Am. Ceram. Soc. 53: 34 (1970).
10. 10. Werme, L., Björner, I. K., Bart, G., Zwicky, H. U., Grambow, B., Lutze, W., Ewing, R. C. and Magrabi, C. Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions. J. Mat. Res. 5: 1130 (1990).