IHLW PCT, Spinel T1%, Electrical Conductivity, and Viscosity Model Development (Final Report)

Technical Report · Wed Nov 13 04:00:00 EST 2013

DOI:https://doi.org/10.2172/1105987· OSTI ID:1105987

Kruger, Albert A. ^[1]; Piepel, Gregory F. ^[1]; Landmesser, S. M. ^[1]; Pegg, I. L. ^[1]; Heredia-Langner, Alejandro ^[1]; Cooley, Scott K. ^[1]; Gan, H. ^[1]; Kot, W. K. ^[1]

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1. Hanford Site (HNF), Richland, WA (United States)

This report is the last in a series of currently scheduled reports that presents the results from the High Level Waste (HLW) glass formulation development and testing work performed at the Vitreous State Laboratory (VSL) of the Catholic University of America (CUA) and the development of IHLW property-composition models performed jointly by Pacific Northwest National Laboratory (PNNL) and VSL for the River Protection Project-Waste Treatment and Immobilization Plant (RPP-WTP). Specifically, this report presents results of glass testing at VSL and model development at PNNL for Product Consistency Test (PCT), one-percent crystal fraction temperature (T1%), electrical conductivity (EC), and viscosity of HLW glasses. The models presented in this report may be augmented and additional validation work performed during any future immobilized HLW (IHLW) model development work. Completion of the test objectives is addressed.

• Research Organization: Hanford Site (HNF), Richland, WA (United States)
• Sponsoring Organization: USDOE Office of Environmental Management (EM)
• Contributing Organization: Department of Energy - Office of River Protection, Pacific Northwest National Laboratory, The Catholic Univsity of America
• DOE Contract Number: AC27-08RV14800
• OSTI ID: 1105987
• Report Number(s): ORP--56320 Rev 0; VSL-07R1240-4
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES