scholarly journals Glass formulation for phase 1 high-level waste vitrification

1996 ◽  
Author(s):  
J.D. Vienna ◽  
P.R. Hrma
Keyword(s):  
Phase 1 ◽  
High Level Waste ◽  
Waste Vitrification ◽  
Glass Formulation ◽  
High Level

scholarly journals High Waste Loading Glass Formulations for Hanford High-Aluminum High-Level Waste Streams

2011 ◽  
Author(s):  
Albert A. Kruger
Keyword(s):  
Previous Experience ◽  
High Level Waste ◽  
Waste Streams ◽  
Testing Program ◽  
Glass Formulation ◽  
Waste Loading ◽  
Production Requirement ◽  
High Level ◽  
Glass Compositions ◽  
High Aluminum

The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable in joule-heated, ceramic-lined melters and meet WTP Contract terms. The WTP’s overall mission will require the immobilization of tank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous (P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility of increases in waste loading from about 25 wt% to 33–50 wt% (based on oxide loading) in the glass depending on the waste stream. It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.

scholarly journals Glass Formulation Development in Support of Melter Testing to Demonstrate Enhanced High Level Waste Throughput

2008 ◽  
Vol 1107 ◽  
Author(s):  
James C. Marra ◽  
Kevin M. Fox ◽  
David K. Peeler ◽  
Thomas B. Edwards ◽  
Amanda L. Youchak ◽  
...  
Keyword(s):  
Product Quality ◽  
Department Of Energy ◽  
High Alumina ◽  
High Level Waste ◽  
Alumina Concentration ◽  
Formulation Development ◽  
Technology Innovations ◽  
Glass Formulation ◽  
Waste Loading ◽  
High Level

AbstractThe U.S. Department of Energy (DOE) is currently processing high-level waste (HLW) through a Joule-heated melter (JHM) at the Savannah River Site (SRS) and plans to vitrify HLW and Low activity waste (LAW) at the Hanford Site. Over the past few years at the Defense Waste Processing Facility (DWPF), work has concentrated on increasing waste throughput. These efforts are continuing with an emphasis on high alumina concentration feeds. High alumina feeds have presented specific challenges for the JHM technology regarding the ability to increase waste loading yet still maintain product quality and adequate throughput. Alternatively, vitrification technology innovations are also being investigated as a means to increase waste throughput. The Cold Crucible Induction Melter (CCIM) technology affords the opportunity for higher vitrification process temperatures as compared to the current reference JHM technology. Higher process temperatures may allow for higher waste loading and higher melt rate.Glass formulation testing to support melter demonstration testing was recently completed. This testing was specifically aimed at high alumina concentration wastes. Glass composition/property models developed for DWPF were utilized as a guide for formulation development. Both CCIM and JHM testing will be conducted so glass formulation testing was targeted at both technologies with a goal to significantly increase waste loading and maintain melt rate without compromising product quality.

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 Design and operating features of the high-level waste vitrification system for the West Valley demonstration project

1986 ◽  
Author(s):  
D.H. Siemens ◽  
M.M. Beary ◽  
S.M. Barnes ◽  
D.N. Berger ◽  
R.A. Brouns ◽  
...  
Keyword(s):  
Demonstration Project ◽  
High Level Waste ◽  
The West ◽  
Waste Vitrification ◽  
High Level

Static Leaching of Radioactive Glass Under Conditions Simulating a Granitic Repository for High-Level Waste: Phase 1.

1983 ◽  
Vol 26 ◽  
Author(s):  
Hans-Peter Hermansson ◽  
Hilbert Christensen ◽  
David E Clark ◽  
Inga-Kari Björner ◽  
Hayaichi Yokoyama ◽  
...  
Keyword(s):  
Phase 1 ◽  
High Level Waste ◽  
Borosilicate Glasses ◽  
Joint Research ◽  
Weight Losses ◽  
Infrared Reflection ◽  
Joint Research Project ◽  
Actinide Oxides ◽  
Leaching Experiments ◽  
High Level

ABSTRACTA joint research project with participation from Japan, Switzerland and Sweden is underway at Studsvik (The JSS-project). The project concerns investigations on the leaching of fully radioactive glass (containing 12 wt% fission product oxides and actinide oxides) manufactured by CEA/Marcoule.So far the glass has been leached in doubly distilled water and in silicate water at 90°C. Some leaching experiments involved the presence of crushed Stripa granite in the same containers as the glass.Due to strong radiation and the presence of plutonium the leaching was carried out in a specially designed lead cave using gilded stainless steel containers.Weight losses, pH and elemental mass losses were determined together with infrared reflection spectral changes. These data are compared to those obtained from a simulated nonradioactive glass of nearly the same composition and to similar alkali borosilicate glasses previously investigated at Studsvik.

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