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Meeting MS&T26: Materials Science & Technology
Symposium Additively Manufactured Materials for Nuclear Energy
Presentation Title Molecular Dynamics Investigation of Helium-Induced Damage in Alloy 800H
Author(s) Thaneshwor Kaloni, Ibrahim Cheik Njifon, Edmanuel Torres
On-Site Speaker (Planned) Thaneshwor Kaloni
Abstract Scope Alloy 800H serves as a key structural material for nuclear reactors. During irradiation, it experiences microstructural degradation arising from irradiation defect accumulation and helium (He) generation, impacting long-term performance. In this work, molecular dynamics simulations were employed to explore the coupled effects of He generation and irradiation-induced defect accumulation in polycrystalline alloy 800H at 600 K. The results indicate that irradiation promotes grain growth. However, decreasing the grain size or increasing the He concentration promotes the stability of the polycrystalline structure. In addition, the increase in He content reduces the dislocation density while promoting the growth of large defect clusters. Structural analysis further revealed that He atoms preferentially aggregate within these large defect clusters, typically bounded by dislocation loops. Finally, we find these effects weaken the mechanical properties of alloy 800H.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Additive Manufacturing of Novel Cobalt-Free Nanoprecipitate-Strengthened High-Entropy Alloys for Nuclear Applications
Combinatorial Synthesis and Machine Learning Assisted Refractory Alloy Design
Comparing Microstructure and Mechanical Behavior of Compacted versus Binder Jet Printed and Sintered Zircaloy-4 Powder
Design and Fabrication of Open-Porous Structures to Advance Nuclear Energy
Feasibility Study on the Production of Fuel Pin Spacer Rings in 316L via Laser Powder Bed Fusion
High-Throughput Screening of Additively Manufactured Multi-Principal Element Alloys for Nuclear Applications
Ion Irradiation Response of Additively Manufactured GRX-810 Medium-Entropy Oxide Dispersion Strengthened Alloy
Irradiation Response of Wire Arc Additively Manufactured 316L Stainless Steel: Process, Microstructure, and Defect Evolution
Laser Powder Bed Fusion of Alumina-Forming Austenitic Steel for Lead-Cooled Fast Reactor Applications: Processing and Corrosion Behaviour
Mechanisms of Microstructural Homogenization, Mechanical Property Evolution, and Proton Irradiation Response in HIP-Treated PBF-LB 316L Stainless Steel for LWR Applications
Mesoscale Modeling of Radiation Damage Evolution in Additively Manufactured Austenitic Stainless Steel
Molecular Dynamics Investigation of Helium-Induced Damage in Alloy 800H
Powder Bed Fusion of Polymer-Ceramic Composites for Neutron Radiation Shielding
Stability of Additively Manufactured GRCop-42 for Nuclear Thermal Propulsion
Stereolithography Additive Manufacturing of Lithium-Containing Ceramics for Fusion Energy: Resin Development, Fabrication, and Sintering
The Integration of Ion-Neutron-Modeling Approaches to Accelerate Adoption of Additively Manufactured Steels for Nuclear Energy
Transforming Fabrication: Enabling Nuclear Innovation Through Additive Technologies
Westinghouse Advancements in Additive Manufacturing of Commercial Nuclear Product

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