High concentrations of Na2O and Al2O3 in the liquid high-level radioactive waste (HLW) stored at the Hanford Site can cause nepheline (NaAlSiO4) to precipitate in a vitrified monolithic waste form upon cooling. Nepheline phase formation removes glass- former SiO2 and -modifier Al2O3 from the immobilization matrix in greater proportion to alkalis, which can reduce glass durability and consequently increase the leach rate of radionuclides into the surrounding environment. Current uncertainty in defining the HLW glass composition region prone to precipitating nepheline necessitates targeting a conservative waste loading, which raises operational costs by extending the liquid radioactive waste disposal mission and increases the required permane...
The development of assessed and consistent phase equilibria and thermodynamic data for major glass c...
AbstractAmong the large number of matrixes explored as hosts for high-level nuclear wastes, conditio...
The Hanford Waste Treatment and Immobilization Plant will vitrify radioactive waste into borosilicat...
High concentrations of Na2O and Al2O3 in the liquid high-level radioactive waste (HLW) stored at the...
Vitrification of sodium and alumina-rich high-level radioactive waste (HLW) into borosilicate glasse...
High-level waste (HLW) glasses with high alumina content are prone to nepheline crystallization duri...
The objective of the proposed effort is to use a new approach to develop solution models of complex ...
High-level radioactive wastes are stored as liquids in underground storage tanks at the Department o...
The crystal-melt equilibria in complex fifteen component melts are modeled based on quasicrystalline...
High-level waste (HLW) glass compositions, processing schemes, limits on waste content, and corrosio...
AbstractA number of waste components in US defense high level radioactive wastes (HLW) have proven c...
High-level waste (HLW) throughput (i.e., the amount of waste processed per unit time) is a function ...
The performance of a glass used for immobilization of high-level nuclear waste (HLW) is generally qu...
The development of assessed and consistent phase equilibria and thermodynamic data for major glass c...
Radioactive wastes on the Hanford Site are going to be permanently disposed of by incorporation into...
The development of assessed and consistent phase equilibria and thermodynamic data for major glass c...
AbstractAmong the large number of matrixes explored as hosts for high-level nuclear wastes, conditio...
The Hanford Waste Treatment and Immobilization Plant will vitrify radioactive waste into borosilicat...
High concentrations of Na2O and Al2O3 in the liquid high-level radioactive waste (HLW) stored at the...
Vitrification of sodium and alumina-rich high-level radioactive waste (HLW) into borosilicate glasse...
High-level waste (HLW) glasses with high alumina content are prone to nepheline crystallization duri...
The objective of the proposed effort is to use a new approach to develop solution models of complex ...
High-level radioactive wastes are stored as liquids in underground storage tanks at the Department o...
The crystal-melt equilibria in complex fifteen component melts are modeled based on quasicrystalline...
High-level waste (HLW) glass compositions, processing schemes, limits on waste content, and corrosio...
AbstractA number of waste components in US defense high level radioactive wastes (HLW) have proven c...
High-level waste (HLW) throughput (i.e., the amount of waste processed per unit time) is a function ...
The performance of a glass used for immobilization of high-level nuclear waste (HLW) is generally qu...
The development of assessed and consistent phase equilibria and thermodynamic data for major glass c...
Radioactive wastes on the Hanford Site are going to be permanently disposed of by incorporation into...
The development of assessed and consistent phase equilibria and thermodynamic data for major glass c...
AbstractAmong the large number of matrixes explored as hosts for high-level nuclear wastes, conditio...
The Hanford Waste Treatment and Immobilization Plant will vitrify radioactive waste into borosilicat...