SOURCE TERM TARGETED THRUST FY 2005 NEW START PROJECTS

Technical Report · Wed Oct 05 00:00:00 EDT 2005

DOI:https://doi.org/10.2172/861320· OSTI ID:861320

NA,

While a significant amount of work has been devoted to developing thermodynamic data. describing the sorption of radionuclides to iron oxides and other geomedia, little data exist to describe the interaction of key radionuclides found in high-level radioactive waste with the uranium surfaces expected in corroded spent nuclear fuel (SNF) waste packages. Recent work indicates that actinide adsorption to the U(VI) solids expected in the engineered barrier system may play a key role in the reduction of dissolved concentrations of radionuclides such as Np(V). However, little is known about the mechanism(s) of adsorption, nor are the thermodynamic data available to represent the phenomenon in predictive modeling codes. Unfortunately, this situation makes it difficult to consider actinide adsorption to the U(VI) silicates in either geochemical or performance assessment (PA) predictions. The primary goal in the Source Term Targeted Thrust area is to ''study processes that control radionuclide release from the waste form''. Knowledge of adsorption of actinides to U(VI) silicate solids its and parameterization in geochemical models will be an important step towards this goal.

• Research Organization: Office of Scientific and Technical Information (OSTI), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: NA
• OSTI ID: 861320
• Report Number(s): NA; MOL.20051121.0007 DC#44839; TRN: US0600638
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDES
ADSORPTION
HIGH-LEVEL RADIOACTIVE WASTES
IRON OXIDES
NUCLEAR FUELS
PERFORMANCE
RADIOISOTOPES
SILICATES
SIMULATION
SORPTION
SOURCE TERMS
THERMODYNAMICS
URANIUM
WASTES
SPENT FUELS