scholarly journals A Strategy to Assess Performance of Selected Low-Activity Waste Forms in an Integrated Disposal Facility

2003 ◽  
Author(s):  
B PETER McGrail ◽  
Diana H Bacon ◽  
R JEFFREY Serne ◽  
Eric M Pierce
Keyword(s):  
Waste Forms ◽  
Disposal Facility ◽  
Low Activity

scholarly journals Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment

2005 ◽  
Author(s):  
Eric M Pierce ◽  
B Peter McGrail ◽  
Larry M Bagaasen ◽  
Elsa A Rodriguez ◽  
Dawn M Wellman ◽  
...  
Keyword(s):  
Performance Assessment ◽  
Laboratory Testing ◽  
Waste Forms ◽  
Disposal Facility ◽  
Low Activity

scholarly journals Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment

2005 ◽  
Author(s):  
Eric M. Pierce ◽  
B. Peter McGrail ◽  
Larry M. Bagaasen ◽  
Elsa A. Rodriguez ◽  
Dawn M. Wellman ◽  
...  
Keyword(s):  
Performance Assessment ◽  
Laboratory Testing ◽  
Waste Forms ◽  
Disposal Facility ◽  
Low Activity

scholarly journals Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment

2006 ◽  
Author(s):  
Eric M. Pierce ◽  
B. Peter McGrail ◽  
Larry M. Bagaasen ◽  
Elsa A. Rodriguez ◽  
Dawn M. Wellman ◽  
...  
Keyword(s):  
Performance Assessment ◽  
Laboratory Testing ◽  
Waste Forms ◽  
Disposal Facility ◽  
Low Activity

Utilization of Radioactive Waste for Solidifying Material to Fill Waste Forms

2001 ◽  
Author(s):  
Takeshi Ishikura ◽  
Daiichiro Oguri
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Filling Ratio ◽  
Improved Method ◽  
Low Level ◽  
Waste Forms ◽  
Disposal Facility ◽  
Low Level Radioactive Waste

Abstract Minimizing the volume of radioactive waste generated during dismantling of nuclear power plants is a matter of great importance. In Japan waste forms buried in shallow burial disposal facility as low level radioactive waste (LLW) must be solidified by cement with adequate strength and must extend no harmful openings. The authors have developed an improved method to minimize radioactive waste volume by utilizing radioactive concrete and metal for mortar to fill openings in waste forms. Performance of a method to pre-place large sized metal or concrete waste and to fill mortar using small sized metal or concrete was tested. It was seen that the improved method substantially increases the filling ratio, thereby decreasing the numbers of waste containers.

Fluidized Bed Steam Reformed (FBSR) Mineral Waste Forms: Characterization and Durability Testing

2006 ◽  
Vol 985 ◽  
Author(s):  
Carol Jantzen ◽  
Troy H. Lorier ◽  
John M. Pareizs ◽  
James C. Marra
Keyword(s):  
Fluidized Bed ◽  
Environmental Protection Agency ◽  
National Laboratory ◽  
Pilot Scale ◽  
Waste Form ◽  
High Sodium ◽  
Waste Forms ◽  
Ring Structures ◽  
Low Activity ◽  
Mineral Waste

AbstractFluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium low activity wastes (LAW) such as those existing at the Hanford site, at the Idaho National Laboratory (INL), and the Savannah River Site (SRS). The addition of clay, charcoal, and a catalyst as co-reactants with the waste denitrates the aqueous wastes and forms a granular mineral waste form that can subsequently be made into a monolith for disposal if necessary. The waste form produced is a multiphase mineral assemblage of Na-Al-Si (NAS) feldspathoid minerals with cage and ring structures and iron bearing spinel minerals. The mineralization occurs at moderate temperatures between 650-750°C in the presence of superheated steam. The cage and ring structured feldspathoid minerals atomically bond radionuclides like Tc-99 and Cs-137 and anions such as SO4, I, F, and Cl. The spinel minerals stabilize Resource Conservation and Recovery Act (RCRA) hazardous species such as Cr and Ni. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low-activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium-bearing waste (SBW) in pilot scale facilities at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The results of the SPFT testing and the activation energies for dissolution are discussed in this study.

Preparation and Properties of Hydroceramic Waste Forms Made with Simulated Hanford Low-Activity Waste

2005 ◽  
Vol 88 (12) ◽  
pp. 3287-3302 ◽  
Author(s):  
Yun Bao ◽  
Michael W. Grutzeck ◽  
Carol M. Jantzen
Keyword(s):  
Waste Forms ◽  
Low Activity

Source-Term Analysis for Hanford Low-Activity Tank Waste Using the Reaction-Transport Code AREST-CT

1996 ◽  
Vol 465 ◽  
Author(s):  
Y. Chen ◽  
B. P. McGrail ◽  
D. W. Engel
Keyword(s):  
Pore Water ◽  
Transport Theory ◽  
Scientific Basis ◽  
Process Models ◽  
Release Rates ◽  
Ion Exchange Reaction ◽  
Disposal Facility ◽  
Reaction Transport ◽  
Term Performance ◽  
Low Activity

ABSTRACTA general, integrated performance assessment code, AREST-CT, was used to analyze the influence of various factors on the release rates of radionuclides from a proposed facility for disposal of low-activity tank wastes. The code couples various process models together based on the framework of reaction-transport theory. The disposal facility was modeled as a 1-D column surrounded by soil. A borosilicate waste glass, LD6–5412 was the waste form considered in the analysis. Included in the simulations were 38 aqueous species, 14 minerals, 21 equilibrium reactions, and 16 kinetic reactions. Dissolution rate of the glass and the release rates of Te, Pu, U, Np, I, Se under different conditions were calculated for 50,000 years. The simulations revealed that 1) open exchange between the atmosphere and pore-water within the vault significantly improves the performance; 2) an ion-exchange reaction between the glass and aqueous phase increases the release rates significantly; and 3) at the hydrogeologie conditions under consideration, variation of the pore-water velocity has little effect on the release rate of radionuclides. These results provide a scientific basis for formulation of waste forms and engineering design of the disposal facility. Reaction-transport modeling can provide information on the long-term performance of disposal systems that are not obtainable from laboratory experiments alone or by conventional decoupled process models.

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