Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C].
Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C].

Author:

Publisher:

Published: 1976

Total Pages:

ISBN-13:

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Volatilities of a zinc borosilicate glass containing 25 wt. percent simulated high-level radioactive waste calcine and of the calcine itself were determined in the range 800 to 1200°C. The fission products Rb, Mo, Ru, Te, and Cs were detected in the vapor from both the glass and the calcine. In general, the vaporization rates were lower from the glass with the exception of Rb and Cs at 1200°C, where the rates were about the same from the glass as from the calcine. Furthermore, slopes of Arrhenius plots for Rb and Cs were higher for the glass indicating that more of these elements would be lost from the glass above 1200°C than from the calcine. Vaporization of all volatile elements from the glass seems to be dominated by a single mechanism; thus, vapor composition over the glass is essentially temperature independent. Several mechanisms apply to vaporization of the various elements from the calcine. Gross weight-loss from the glass and calcine appears to be surface and diffusion controlled, respectively.

NUREG/CR.
NUREG/CR.

Author: U.S. Nuclear Regulatory Commission

Publisher:

Published: 1979

Total Pages: 316

ISBN-13:

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Scientific Basis for Nuclear Waste Management
Scientific Basis for Nuclear Waste Management

Author: Clyde J. Northrup

Publisher: Springer

Published: 2013-12-19

Total Pages: 932

ISBN-13: 1468438395

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The Symposium on the Scientific Basis for Nuclear Waste Manage ment was held in the fall of 1979 in Boston, Massachusetts and was one of a number of symposia included in the Annual Meeting of the Materials Research Society. The thrust of this annual Symposium is unique in the area of waste management. Recognizing that this is an area of great complexity which requires contributions from scien tists with many different backgrounds some of which are not normally associated with nuclear energy, the Materials Research Society pro vides a forum for discussions of a wide range of materials behavior and transport phenomena. As can be seen from the list of references in each paper, the authors draw heavily on contributions associated with professional societies in addition to the Materials Research Society, and this annual meeting encourages the cross-fertilization between disciplines that are essential to an adequate treatment of the problems associated with nuclear waste management. The proceed ings of the first Symposium that was held in 1978 was designated as Volume 1 in this series. The third Symposium is scheduled for 1980. The scope of the 1979 Symposium was guided by the Steering Committee: R. L. Schwoebel, Sandia Laboratories, USA (Chairman) W. Carbiener, Battelle Memorial Institute, Columbus, USA D. Ferguson, Oak Ridge National Laboratory, USA W. Heimerl, DWK, Mol, Belgium W. Lutze, Hahn Meitner Institut, Berlin, W. Germany J. D. Mather, Institute of Geological Sciences, Harwell, UK G. Oertel, Department of Energy, USA R.