scholarly journals A Method for Determining Bulk Density, Material Density, and Porosity of Melter Feed During Nuclear Waste Vitrification

2015 ◽  
Vol 99 (1) ◽  
pp. 98-105 ◽  
Author(s):  
Zachary Hilliard ◽  
Pavel Hrma
Keyword(s):  
Bulk Density ◽  
Nuclear Waste ◽  
Material Density ◽  
Waste Vitrification

Nuclear Waste Vitrification

2021 ◽  
pp. 1205-1218
Author(s):  
Olivier Pinet ◽  
Etienne Vernaz ◽  
Christian Ladirat ◽  
Stéphane Gin
Keyword(s):  
Nuclear Waste ◽  
Waste Vitrification

scholarly journals The role of frit in nuclear waste vitrification

1994 ◽  
Author(s):  
J.D. Vienna ◽  
P.A. Smith ◽  
D.A. Dorn ◽  
P. Hrma
Keyword(s):  
Nuclear Waste ◽  
Waste Vitrification

scholarly journals Nonintrusive Depth Estimation of Buried Radioactive Wastes Using Ground Penetrating Radar and a Gamma Ray Detector

2019 ◽  
Vol 11 (2) ◽  
pp. 141 ◽  
Author(s):  
Ikechukwu Ukaegbu ◽  
Kelum Gamage ◽  
Michael Aspinall
Keyword(s):  
Bulk Density ◽  
Ground Penetrating Radar ◽  
Gamma Ray ◽  
Depth Estimation ◽  
Average Error ◽  
Density Estimates ◽  
Material Density ◽  
Linear Correction ◽  
Ground Penetrating ◽  
Gamma Ray Detector

This study reports on the combination of data from a ground penetrating radar (GPR) and a gamma ray detector for nonintrusive depth estimation of buried radioactive sources. The use of the GPR was to enable the estimation of the material density required for the calculation of the depth of the source from the radiation data. Four different models for bulk density estimation were analysed using three materials, namely: sand, gravel and soil. The results showed that the GPR was able to estimate the bulk density of the three materials with an average error of 4.5%. The density estimates were then used together with gamma ray measurements to successfully estimate the depth of a 658 kBq ceasium-137 radioactive source buried in each of the three materials investigated. However, a linear correction factor needs to be applied to the depth estimates due to the deviation of the estimated depth from the measured depth as the depth increases. This new application of GPR will further extend the possible fields of application of this ubiquitous geophysical tool.

scholarly journals Application of evolved gas analysis to cold-cap reactions of melter feeds for nuclear waste vitrification

2014 ◽  
Vol 592 ◽  
pp. 86-92 ◽  
Author(s):  
Carmen P. Rodriguez ◽  
Jaehun Chun ◽  
Michael J. Schweiger ◽  
Albert A. Kruger ◽  
Pavel Hrma
Keyword(s):  
Nuclear Waste ◽  
Evolved Gas Analysis ◽  
Gas Analysis ◽  
Evolved Gas ◽  
Waste Vitrification

Nepheline Crystallization in High-Alumina High-Level Waste Glass

2015 ◽  
Vol 1744 ◽  
pp. 85-91 ◽  
Author(s):  
José Marcial ◽  
John McCloy ◽  
Owen Neill
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
High Alumina ◽  
High Level Waste ◽  
Interfacial Conditions ◽  
Waste Vitrification ◽  
Cooling Schedules ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Glass Compositions

ABSTRACTThe understanding of the crystallization of aluminosilicate phases in nuclear waste glasses is a major challenge for nuclear waste vitrification. Robust studies on the compositional dependence of nepheline formation have focused on large compositional spaces with hundreds of glass compositions. However, there are clear benefits to obtaining complete descriptions of the conditions under which crystallization occurs for specific glasses, adding to the understanding of nucleation and growth kinetics and interfacial conditions. The focus of this work was the investigation of the microstructure and composition of one simulant high-level nuclear waste glass crystallized under isothermal and continuous cooling schedules. It was observed that conditions of low undercooling, nepheline was the most abundant aluminosilicate phase. Further undercooling led to the formation of additional phases such as calcium phosphate. Nepheline composition was independent of thermal history.

scholarly journals Conceptual design of a nuclear waste vitrification facility

1978 ◽  
Author(s):  
D.E. Larson ◽  
H.T. Blair ◽  
W.F. Bonner ◽  
A.A. Garrett ◽  
M.S. Hanson ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Nuclear Waste ◽  
Waste Vitrification

CFD Modeling of Thermal Effects of Nuclear Waste Vitrification Processes

2006 ◽  
Author(s):  
Chris Rayner ◽  
Mehdi Soltani ◽  
Chris Barringer ◽  
Kelly J. Knight
Keyword(s):  
Nuclear Waste ◽  
Waste Treatment ◽  
Treatment Plant ◽  
Cfd Modeling ◽  
Hvac System ◽  
System Specification ◽  
Air Temperatures ◽  
Waste Vitrification ◽  
Waste Treatment Plant ◽  
Computational Fluid Dynamics Cfd

The Waste Treatment Plant (WTP) at Hanford, WA will vitrify nuclear waste stored at the DOE Hanford facility. The vitrification process will take place in two large concrete buildings where the glass is poured into stainless steel canisters or containers and allowed to cool. Computational Fluid Dynamics (CFD) was used extensively to calculate the effects of the heat released by molten glass as it is poured and cooled, on the HVAC system and the building structure. CFD studies of the glass cooling in these facilities were used to predict canister temperatures, HVAC air temperatures, concrete temperatures and insulation requirements, and design temperatures for canister handling equipment and instrumentation at various stages of the process. These predictions provided critical input in the design of the HVAC system, specification of insulation, the design of canister handling equipment, and the selection of instrumentation.

Machine learning to predict refractory corrosion during nuclear waste vitrification

MRS Advances ◽  
2021 ◽  
Author(s):  
Natalie J. Smith-Gray ◽  
Irmak Sargin ◽  
Scott Beckman ◽  
John McCloy
Keyword(s):  
Machine Learning ◽  
Nuclear Waste ◽  
Waste Vitrification ◽  
Refractory Corrosion
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