Long term corrosion behaviour of the WAK-HLW glass in salt solutions

Waste Management

Volumn 17, Issue 7, 1998, Pages 429-436

  Luckscheiter, B ^a   Nesovic, M ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

CORROSION; DIFFUSION IN SOLIDS; DISSOLUTION; GLASS; NUCLEAR FUEL REPROCESSING; PH EFFECTS; RADIOACTIVE WASTES; RADIOISOTOPES; SODIUM CHLORIDE;

LONG TERM CORROSION; MATRIX DISSOLUTION;

INDUSTRIAL WASTE TREATMENT;

CORROSION; GLASS; SALT;

ARTICLE; CHEMICAL REACTION KINETICS; CORROSION; DEGRADATION; DIFFUSION; GLASS INDUSTRY; PH; PRIORITY JOURNAL; REACTION ANALYSIS; TECHNOLOGY;

EID: 0031837729     PISSN: 0956053X     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0956-053X(97)10027-7     Document Type: Article

References (7)

1. 1. Luckscheiter, B. and Nesovic, M. Development of glasses for the vitrification of HLLW in a Joule-heated ceramic. Waste Management 16: 571-578 (1997).
2. 2. Grambow, B., Lutze, W. and Müller, R. Empirical dissolution rate law for the glass R7T7 contacting halite- and silica-saturated brines. In Scientific Basis for Nuclear Waste Management XV, ed. C. G. Sombret MRS Symposium Proceedings 257: 143-150. Materials Research Society, Pittsburgh PA (1992).
3. 3. Grambow, B. and Müller, R. Chemistry of glass corrosion in high saline brines. In Scientific Basis for Nuclear Waste Management XIII, eds. V. M. Oversby and P. W. Brown. MRS Symposium Proceedings 176: 229-240. Materials Research Society, Pittsburgh PA (1989).
4. 4. Lutze, W. and Grambow, B. The Effect of Glass Corrosion on Near Field Chemistry. Radiochimica Acta 58/59: 3-7 (1992).
5. 5. Abdelouas, A., Crovisier, J. L., Lutze, W., Müller, R. and Bernotat, W. Structure and chemical properties of surface layers developed on R7T7 simulated nuclear waste glass altered in brine at 190°C. European Journal of Mineralogy 7: 1101-1113 (1995).
6. 6. Abrajano, T. A. and Bates, J. K. Transport and reaction kinetics at the glass: solution interface region: Results of repository-oriented leaching experiments. In Scientific Basis for Nuclear Waste Management X, eds J. K. Bates and W. B. Seefeldt. MRS Symposium Proceedings 84: 533-546. Materials Research Society, Pittsburgh PA (1987).
7. 7. Rother, A., Lutze, W. and Schubert, P. Characterization of lanthanoid phases formed upon glass dissolution in salt solutions. In Scientific Basis for Nuclear Waste Management XV, ed. C. G. Sombret. MRS Symposium Proceedings 257: 57-64. Materials Research Society, Pittsburgh PA (1992).