Small-scale crucible melting tests on simulated waste glass were performed with technetium-99 (Tc-99) introduced as different species in a representative low activity waste simulant. The glass saw an increase in Tc-99 retention when TcO2 center dot 2H(2)O and various Tc-minerals containing reduced tetravalent Tc were used compared to tests in which pertechnetate with heptavalent Tc was used. We postulate that the increase of Tc retention is likely caused by different reaction paths for Tc incorporation into glass during early stages of melting, rather than the low volatility of reduced tetravalent Tc compounds, which has been a generally accepted idea. Additional studies are needed to clarify the exact mechanisms relevant to the effect of r...
This study focused on the potential impacts of the addition of Crystalline Silicotitanate (CST) and ...
Results of leach tests with Tc-99 doped SRP borosilicate waste glass are presented. The glass was pr...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...
Small-scale crucible melting tests on simulated waste glass were performed with technetium-99 (Tc-99...
Small-scale crucible melting tests on simulated waste glass were performed with technetium-99 (Tc-99...
A glass that has been tested to understand the corrosion behavior of waste glasses with high soda co...
Technetium-99 is an abundant, long-lived (t1/2 = 213,000 yr) fission product that creates challenge...
The behavior of non-pertechnetate (Tc(I)) species was studied by preparing three portions of dried l...
Technetium (Tc-99) immobilization by doping into iron oxide mineral phases may alleviate the problem...
Thesis (Ph.D.), Chemistry, Washington State UniversityA priority of the United States Department of ...
Laboratory tests are being, conducted using two radionuclide-doped Defense Waste Processing, Facilit...
Technetium (99Tc, half-life = 2.13x105 years, ?-emitter) is one of the radionuclides of major concer...
Technetium ({sup 99}Tc, half-life = 2.13 x 10{sup 5} years, ?-emitter) is one of the radionuclides o...
Abstract Nearly 100 tests were performed with proto-typical melters and off-gas system components to...
The objective of this research is to increase the knowledge of the fundamental technetium chemistry ...
This study focused on the potential impacts of the addition of Crystalline Silicotitanate (CST) and ...
Results of leach tests with Tc-99 doped SRP borosilicate waste glass are presented. The glass was pr...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...
Small-scale crucible melting tests on simulated waste glass were performed with technetium-99 (Tc-99...
Small-scale crucible melting tests on simulated waste glass were performed with technetium-99 (Tc-99...
A glass that has been tested to understand the corrosion behavior of waste glasses with high soda co...
Technetium-99 is an abundant, long-lived (t1/2 = 213,000 yr) fission product that creates challenge...
The behavior of non-pertechnetate (Tc(I)) species was studied by preparing three portions of dried l...
Technetium (Tc-99) immobilization by doping into iron oxide mineral phases may alleviate the problem...
Thesis (Ph.D.), Chemistry, Washington State UniversityA priority of the United States Department of ...
Laboratory tests are being, conducted using two radionuclide-doped Defense Waste Processing, Facilit...
Technetium (99Tc, half-life = 2.13x105 years, ?-emitter) is one of the radionuclides of major concer...
Technetium ({sup 99}Tc, half-life = 2.13 x 10{sup 5} years, ?-emitter) is one of the radionuclides o...
Abstract Nearly 100 tests were performed with proto-typical melters and off-gas system components to...
The objective of this research is to increase the knowledge of the fundamental technetium chemistry ...
This study focused on the potential impacts of the addition of Crystalline Silicotitanate (CST) and ...
Results of leach tests with Tc-99 doped SRP borosilicate waste glass are presented. The glass was pr...
Fission products and minor actinides are currently immobilized by vitrification in a borosilicate gl...