- Cited by 54
Williams, Quentin and Williams, KevinJon 1991. Leakage from vitrified radioactive waste. The Lancet, Vol. 337, Issue. 8744, p. 791.
Zwicky, H.U. Graber, TH. Grauer, R. and Restani, R. 1991. Cationic Corrosion Inhibitors for Alkaliborosilicate Glass. MRS Proceedings, Vol. 257, Issue. ,
Grambow, B. Lutze, W. and Müller, R. 1991. Empirical Dissolution Rate Law for the Glass R7T7 Contacting Halite- and Silica-Saturated Brines. MRS Proceedings, Vol. 257, Issue. ,
Petit, Jean-Claude 1992. Natural analogues for the design and performance assessment of radioactive waste forms: A review. Journal of Geochemical Exploration, Vol. 46, Issue. 1, p. 1.
Creach, M. and Magonthier, M.C. 1992. Retention of radionuclides in poorly organized phases in the near field of a HLW nuclear disposal facility. Applied Clay Science, Vol. 7, Issue. 1-3, p. 59.
Feng, X. Bates, J. K. Bradley, C. R. and Buck, E. C. 1992. Does Fully Radioactive Glass Behave Differently than Simulated Waste Glass?. MRS Proceedings, Vol. 294, Issue. ,
Feng, Xiangdong 1993. Surface Layer Effects on Waste Glass Corrosion. MRS Proceedings, Vol. 333, Issue. ,
Buck, E. C. Fortner, J. A. Bates, J. K. Feng, X. L Dietz, N. Bradley, C. R. and Tani, B. S. 1993. Analytical Electron Microscopy Examination of Solid Reaction Products in Long-Term Tests of Srl 200 Waste Glasses. MRS Proceedings, Vol. 333, Issue. ,
Bates, John K. and Buck, Edgar C. 1993. Waste Glass Weathering. MRS Proceedings, Vol. 333, Issue. ,
Wronkiewicz, D. J. 1993. Radionuclide Decay Effects on Waste Glass Corrosion. MRS Proceedings, Vol. 333, Issue. ,
Feng, Xiangdong Bates, John K. Buck, Edgar C. Bradley, Charles R. and Gong, Meiling 1993. Long-Term Comparison of Dissolution Behavior Between Fully Radioactive and Simulated Nuclear Waste Glasses. Nuclear Technology, Vol. 104, Issue. 2, p. 193.
INAGAKI, Yaohiro FURUYA, Hirotaka IDEMITSU, Kazuya YONEZAWA, Shigeaki NISHIKAWA, Sataro and TAKADA, Jitsuya 1994. Corrosion Behavior of a Powdered Simulated Nuclear Waste Glass in the Presence of Bentonite. Journal of Nuclear Science and Technology, Vol. 31, Issue. 9, p. 948.
Inagaki, Y. Furuya, H. Idemitsu, K. and Yonezawa, S. 1994. Corrosion behavior of a powdered simulated nuclear waste glass: A corrosion model including diffusion process. Journal of Nuclear Materials, Vol. 208, Issue. 1-2, p. 27.
Mchale, J. M. and Coppa, N. V. 1995. Instantaneous Formation of Synroc-B Phases at Ambient Pressure. MRS Proceedings, Vol. 412, Issue. ,
Luckscheiter, B. and Nesovic, M. 1996. Development of glasses for the vitrification of high level liquid waste (HLLW) in a joule heated ceramic melter. Waste Management, Vol. 16, Issue. 7, p. 571.
Shuttleworth, S. and Monteith, J. E. 1996. The Use of Laser Microprobe-ICP-MS in the Examination of Nuclear Waste Glasses. MRS Proceedings, Vol. 465, Issue. ,
Newsom, Horton E. and Hagerty, Justin J. 1997. Chemical components of the Martian soil: Melt degassing, hydrothermal alteration, and chondritic debris. Journal of Geophysical Research: Planets, Vol. 102, Issue. E8, p. 19345.
Macfarlane, Allison 1998. Immobilization of excess alternative to glass. Science & Global Security, Vol. 7, Issue. 3, p. 271.
Jarzemba, Mark S. 1998. Estimating Heat Generation Rates for Wastes Contaminated Primarily by 137Cs and 90Sr. Nuclear Technology, Vol. 124, Issue. 1, p. 82.
Ewing, R. C. 1999. Nuclear waste forms for actinides. Proceedings of the National Academy of Sciences, Vol. 96, Issue. 7, p. 3432.
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This review summarizes the results of the joint Japanese (Central Research Institute of Electric Power Industry, CRIEPI, Tokyo), Swiss (National Cooperative for the Storage of Radioactive Waste, NAGRA, Baden), Swedish (Swedish Nuclear Fuel and Waste Management Company, SKB, Stockholm) international ‘JSS’ project on the determination of the chemical durability of the French nuclear waste borosilicate glass, which was completed in 1988. Radioactive and nonradioactive glass specimens were investigated. A data base was created with results from glass corrosion tests performed with different water compositions, pH values, temperatures, sample surface areas (S), solution volumes (V), and flow rates. Glass corrosion tests were performed with and without bentonite and/or steel corrosion products present. Variation of the glass composition was taken into account by including the borosilicate glass ‘MW’ in the investigations, formulated by British Nuclear Fuels, plc. An understanding was achieved of the glass corrosion process in general, and of the performance of the French glass under various potential disposal conditions in particular. A special effort was made to establish a corrosion data base, using high S/V ratios in the experiments in order to understand the glass durability in the long term.
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