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Meeting MS&T26: Materials Science & Technology
Symposium Ceramics and Glasses for Nuclear Energy Applications
Presentation Title Revisiting Radioiodine Sorbent Regeneration
Author(s) Karthikeyan Baskaran, Jade Beland, Paige Murray, Zac Flandermeyer, Judith Mendoza-Castro, Harmony S Werth, Sungsik Lee, Brian J Riley, Jeffrey D Rimer, Dev Chidambaram, Krista Carlson
On-Site Speaker (Planned) Zac Flandermeyer
Abstract Scope Three commercially available silver sorbents were investigated for regeneration and reuse as primary bed sorbents for radioiodine (I-129) during aqueous reprocessing of used nuclear fuel (UNF). IONEX Ag-400 (Ag-exchanged faujasite), IONEX NexSorb-99 (Ag-exchanged mordenite), and Clariant AC-6120 (Ag impregnated alumina) underwent cyclic iodine loading and regeneration to understand material performance. Ag-400 experienced the highest iodine uptake across all cycles, but the engineered form started to degrade after the first cycle due to AgI(s) formation during loading and transformation to Ag0(s) significantly decreasing mechanical stability. NexSorb-99 demonstrated moderate iodine uptake during cycling without observable change of the engineered form. AC-6120 exhibited the lowest iodine uptake and was also without observable change of the engineered form. NexSorb-99 and AC-6120, both demonstrated mechanical stability of the engineered form across cycling, AC-6120 had higher AgI(s) retention, indicating incomplete sorbent regeneration. The structure-property-performance relationship of the sorbents will be discussed.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Addressing Integration and Compatibility Challenges in SiC-Based Materials for Fusion Applications
Analysis of Crucible-Scale Corrosion Testing of Monofrax® K-3 Refractory in Contact with Glass Melts
Decoding the Structure of Transition Metal Cations Containing Aluminoborosilicate-Based Nuclear Waste Glasses
Densification Mechanisms of Oxide Cermets Sintered by Spark Plasma Sintering for Nuclear Waste Form Application
Design Defects in Nuclear Fuels Using Boron Neutron Capture Method
Effects of Swift Heavy Ion Irradiation on the Oxidation Behavior of Zirconium Carbide
From Irradiation Defects to Thermal Conductivity: A Defect-Informed Model for He Ion-Irradiated Ceria
Impact of MgO on Nepheline Crystallization in Sodium Aluminoborosilicate Glasses
Impact of Potassium on Structure, Chemical Durability, and Nepheline Crystallization of Sodium Aluminoborosilicate Glasses
Impact of Radiation Damage in Uranium Dioxide: Integrating Rate Theory Defect Evolution with Irradiated Annealed Sample
Impact of Vanadium on Structure and Properties of Sodium Aluminoborosilicate Glasses
In-Situ TEM Observation of Irradiation-Induced Basal Plane Formation and Ordering in Nuclear Graphite
Influence of Compositional Complexity on the Structural Integrity of Residual (SIR) and Chemical Leaching Behavior in Nuclear Waste Glasses
International Advances in Glass Waste Forms for Low- and Intermediate-Level Radioactive Waste
Investigating the Impact of BiPO4 on Sulfur Solubility in Sodium Aluminoborosilicate Glasses
K-1: Size Effects on Oxidation Behaviors of IG-110 Nuclear Graphite During Water Vapor Ingress Accidents for High Temperature Gas-Cooled Reactors
Key Synergies in Zirconium Carbide (ZrC) and its Alloying with Uranium (U,Zr)C for Nuclear Fuel Applications
Microstructural Characterization and Melt Composition Changes During Corrosion of Monofrax® K-3 in HLW Glasses
Processing, Properties, and Irradiation Response of ε-W2B5 Based Ceramics for Compact Fusion Reactor Shielding
Pyrolysis of Polymer-Derived SiC Coatings on Surrogate TRISO Fuel Particles
Revisiting Radioiodine Sorbent Regeneration
Sintered SiC and its Potential in Nuclear Energy Applications
Sorbent Characterization and Method Development for Mercury Capture for the Hanford WTP
Structure of MoO3 Containing Alkali Aluminoborophosphate Glasses

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