Test Plan for Glass Melter System Technologies for Vitrification of High-sodium Content Low-level Radioactive Liquid Waste, Project No. RDD-43288

Test Plan for Glass Melter System Technologies for Vitrification of High-sodium Content Low-level Radioactive Liquid Waste, Project No. RDD-43288

Author:

Publisher:

Published: 1995

Total Pages: 80

ISBN-13:

DOWNLOAD EBOOK

This document provides a test plan for the conduct of combustion fired cyclone vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System, Low-Level Waste Vitrification Program. The vendor providing this test plan and conducting the work detailed within it is the Babcock & Wilcox Company Alliance Research Center in Alliance, Ohio. This vendor is one of seven selected for glass melter testing.


Test Plan for Evaluation of Plasma Melter Technology for Vitrification of High-sodium Content Low-level Radioactive Liquid Wastes

Test Plan for Evaluation of Plasma Melter Technology for Vitrification of High-sodium Content Low-level Radioactive Liquid Wastes

Author:

Publisher:

Published: 1994

Total Pages: 84

ISBN-13:

DOWNLOAD EBOOK

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D.F. McLaughlin, E.J. Lahoda, W.R. Gass, and N. D'Amico. The WSTC Program Manager for this test is D.F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.


Vitrification as a Low-level Radioactive Mixed Waste Treatment Technology at Argonne National Laboratory

Vitrification as a Low-level Radioactive Mixed Waste Treatment Technology at Argonne National Laboratory

Author:

Publisher:

Published: 1995

Total Pages: 13

ISBN-13:

DOWNLOAD EBOOK

Argonne National Laboratory-East (ANL-E) is developing plans to use vitrification to treat low-level radioactive mixed wastes (LLMW) generated onsite. The ultimate objective of this project is to install a full-scale vitrification system at ANL-E capable of processing the annual generation and historic stockpiles of selected LLMW streams. This project is currently in the process of identifying a range of processible glass compositions that can be produced from actual mixed wastes and additives, such as boric acid or borax. During the formulation of these glasses, there has been an emphasis on maximizing the waste content in the glass (70 to 90 wt %), reducing the overall final waste volume, and producing a stabilized low-level radioactive waste glass. Crucible glass studies with actual mixed waste streams have produced alkali borosilicate glasses that pass the Toxic Characteristic Leaching Procedure (TCLP) test. These same glass compositions, spiked with toxic metals well above the expected levels in actual wastes, also pass the TCLP test. These results provide compelling evidence that the vitrification system and the glass waste form will be robust enough to accommodate expected variations in the LLMW streams from ANL-E. Approximately 40 crucible melts will be studied to establish a compositional envelope for vitrifying ANL-E mixed wastes. Also being determined is the identity of volatilized metals or off-gases that will be generated.


Test Plan

Test Plan

Author:

Publisher:

Published: 1995

Total Pages: 72

ISBN-13:

DOWNLOAD EBOOK

This document provides a test plan for the conduct of vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384215] is GTS Duratek, Inc., Columbia, Maryland. The GTS Duratek project manager for this work is J. Ruller. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a DuraMelter{trademark} vitrification system.


FY-97 Operations of the Pilot-scale Glass Melter to Vitrify Simulated ICPP High Activity Sodium-bearing Waste

FY-97 Operations of the Pilot-scale Glass Melter to Vitrify Simulated ICPP High Activity Sodium-bearing Waste

Author:

Publisher:

Published: 1997

Total Pages: 56

ISBN-13:

DOWNLOAD EBOOK

A 3.5 liter refractory-lined joule-heated glass melter was built to test the applicability of electric melting to vitrify simulated high activity waste (HAW). The HAW streams result from dissolution and separation of Idaho Chemical Processing Plant (ICPP) calcines and/or radioactive liquid waste. Pilot scale melter operations will establish selection criteria needed to evaluate the application of joule heating to immobilize ICPP high activity waste streams. The melter was fabricated with K-3 refractory walls and Inconel 690 electrodes. It is designed to be continuously operated at 1,150 C with a maximum glass output rate of 10 lbs/hr. The first set of tests were completed using surrogate HAW-sodium bearing waste (SBW). The melter operated for 57 hours and was shut down due to excessive melt temperatures resulting in low glass viscosity (