Vitrification of Hanford Wastes in a Joule-heated Ceramic Melter and Evaluation of Resultant Canisterized Product
Vitrification of Hanford Wastes in a Joule-heated Ceramic Melter and Evaluation of Resultant Canisterized Product

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Publisher:

Published: 1979

Total Pages:

ISBN-13:

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Experience gained in the week-long vitrification test and characterization of the glass produced in the run support the following conclusions: The Hanford waste simulated in this test can be readily vitrified in a joule-heated ceramic melter. Physical properties of the molten glass were entirely compatible with melter operation. The average feed rate of 106 kg/h is high enough to make the ceramic melter a feasible piece of equipment for vitrifying Hanford wastes. The glass produced in this trial had good chemical durability, 6(10)−5 g/cm2-d. When one of the canisters was purposely dropped onto a steel pad, the damage was limited to deformation of the steel can in the impact area, cracking of a weld, and fracturing of glass in the immediate vicinity of the impact area. No glass was released from the canister as a result of the drop test. The results of this vitrification test support the technical feasibility of vitrifying Hanford wastes by means of a joule-heated ceramic melter. Surface area for large glass castings is equivalent to the mass median particle diameters between 4.27 cm (1.75 in.) and 8.91 cm (3.51 in.) even when allowed to cool rapidly by standing in ambient air. Large canisters (up to 0.91 m in dia) can be cast without large voids while standing in air if the fill rate is over 100 kg/h. 34 figures, 10 tables.

ONWI-2
ONWI-2

Author: Battelle Memorial Institute. Office of Nuclear Waste Isolation. Library

Publisher:

Published: 1980

Total Pages: 132

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.