Download or read book Small scale joule heated melting of Savannah River Plant waste glass I factors affecting large scale vitrification tests written by M. J. Plodinec and published by . This book was released on 1979 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Small scale Joule heated Melting of Savannah River Plant Waste Glass I Factors Affecting Large scale Vitrification Tests written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A promising method of immobilizing SRP radioactive waste solids is incorporation in borosilicate glass. In the reference vitrification process, called joule-heated melting, a mixture of glass frit and calcined waste is heated by passage of an electric current. Two problems observed in large-scale tests are foaming and formation of an insoluble slag. A small joule-heated melter was designed and built to study problems such as these. This report describes the melter, identifies factors involved in foaming and slag formation, and proposes ways to overcome these problems.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1989 with total page 1470 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Catalog of United States Government Publications written by and published by . This book was released on 1980-10 with total page 1180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1980 with total page 1542 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Assessment of Savannah River Borosilicate Glass in the Repository Environment written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Since 1973, borosilicate glass has been studied as a matrix for the immobilization of high-level radioactive waste generated at the Savannah River Plant (SRP). In 1977, efforts began to develop and test the large-scale equipment necessary to convert the alkaline waste slurries at SRP into a durable borosilicate glass. A process has now been developed for the proposed Defense Waste Processing Facility (DWPF) which will annually produce approximately 500 canisters of SRP waste glass which will be stored on an interim basis on the Savannah River site. Current national policy calls for the permanent disposal of high-level waste in deep geologic repositories. In the repository environment, SRP waste glass will eventually be exposed to such stresses as lithostatic or hydrostatic pressures, radiation fields, and self-heating due to radioactive decay. In addition, producing and handling each canister of glass will also expose the glass to thermal and mechanical stresses. An important objective of the extensive glass characterization and testing programs of the Savannah River Laboratory (SRL) has been to determine how these stresses affect the performance of SRP waste glass. The results of these programs indicate that: these stresses will not significantly affect the performance of borosilicate glass containing SRP waste; and SRP waste glass will effectively immobilize hazardous radionuclides in the repository environment.
Download or read book VITRIFICATION OF HIGH LEVEL WASTE AT THE SAVANNAH RIVER SITE written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this study was to experimentally measure the properties and performance of a series of glasses with compositions that could represent high level waste Sludge Batch 5 (SB5) as vitrified at the Savannah River Site Defense Waste Processing Facility. These data were used to guide frit optimization efforts as the SB5 composition was finalized. Glass compositions for this study were developed by combining a series of SB5 composition projections with a group of candidate frits. The study glasses were fabricated using depleted uranium and their chemical compositions, crystalline contents and chemical durabilities were characterized. Trevorite was the only crystalline phase that was identified in a few of the study glasses after slow cooling, and is not of concern as spinels have been shown to have little impact on the durability of high level waste glasses. Chemical durability was quantified using the Product Consistency Test (PCT). All of the glasses had very acceptable durability performance. The results of this study indicate that a frit composition can be identified that will provide a processable and durable glass when combined with SB5.
Download or read book Incorporation of Savannah River Plant Radioactive Waste Into Glass written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Processing Variables on the Product Quality of Large scale Glass Forms Containing Simulated SRP Waste written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The reference process for disposal of radioactive waste from the Savannah River Plant is immobilization in borosilicate glass. Full-scale canisters containing simulated waste have been made by two processes: in-can melting and continuous joule-heated melting. For each process, melter atmosphere and the degree of feed mixing have been varied. The effects of these variations on glass quality parameters such as leach rate, degree of fracture and porosity, and amount of crystalline material are discussed.
Download or read book Evaluation of Glass as a Matrix for Solidification of Savannah River Plant Waste written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Laboratory tests using actual sludges collected from Savannah River Plant (SRP) waste tanks were performed to evaluate glass as a waste solidification matrix. Sludge was collected from three SRP waste tanks, washed to remove soluble salts, and then ground to a fine powder. From 25 to 40 wt percent of these sludges was vitrified into a borosilicate glass by melting at 1150$sup 0$C. Substitution of 4 wt percent Li$sub 2$O for 4 wt percent Na$sub 2$O in the glass mix allowed higher loading of a high-aluminum sludge. No problems with phase separation were encountered, and all sludge components, except mercury which volatilized, appeared to dissolve completely in the glass melt. Volatilization of radionuclides during melting was 0.3 percent for $sup 137$Cs, 2.9 percent for $sup 106$Ru, and less than or equal to 0.01 percent for other nuclides. Initial leachabilities of glass products were low: 10$sup -6$ to 10$sup -5$ g/(cm$sup 2$-day) for $sup 137$, $sup 90$Sr, and alpha activity. Leachabilities decreased to 10$sup -8$ to 10$sup -7$ g/(cm$sup 2$- day) in approximately 2 weeks. Heating the glasses at 600$sup 0$C for 1 month caused devitrification which increased leachability, but durable waste forms still remained. This work showed that vitrification of SRP high-level waste sludges in borosilicate glass is feasible. Further investigation of melting concepts, scale- up, cost, long-term stability, and other factors are planned as a part of the development program for long-term waste management. (auth).
Download or read book Vitrification of Waste Containing Salts written by and published by . This book was released on 1995 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Technologies are currently being developed by U.S. Department of Energy's nuclear waste sites to immobilize low-level and hazardous wastes for permanent or long-term disposal. This report describes recent efforts made at the Savannah River Site to examine the effects of salts on vitrification. Statistically designed screening experiments were performed to examine the solubility of several salt species in glass. The corrosion behavior of typical glass melter materials in glass melts containing high salt concentrations was also studied.
Download or read book Evaluation of glass as a matrix for solidification of Savannah River plant waste nonradioactive and tracer studies written by J. A. Kelley and published by . This book was released on 1975 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of Glass as a Matrix for Solidifying Savannah River Plant Waste written by M. J. Plodinec and published by . This book was released on 1979 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of Glass as a Matrix for Solidification of Savannah River Plant Waste Nonradioactive and Tracer Studies written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radioactive Waste Processing and Disposal written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 908 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of glass as a matrix for solidifying Savannah River Plant waste written by M. J. Plodinec and published by . This book was released on 1979 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Bench scale Vitrification Studies with Savannah River Site Mercury written by and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
