SEDL / Topics / Nuclear, Solar, and Geothermal Energy / Recent 25 JAI
Boiling Heat Transfer: An Overview of Longstanding and New Challenges
Modeling Vertical Subcooled Boiling Flows at Low Pressures
Effects of Secondary Phase Particle Dissolution on the In-Reactor Performance of BWR Cladding
Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall
Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials
Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels
Interrelationship between True Stress–True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel
Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals
Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview
Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux
International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
Unusual Enhancement of Ductility Observed During Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350
Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor
Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR
Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels
Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
Effect of Ta Rich Inclusions and Microstructure Change During Precracking on Bimodal Fracture of Reduced-Activation Ferritic/Martensitic Steels Observed in Transition Range
Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments
Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches
Investigation of Material Fatigue Behavior Through Cyclic Ball Indentation Testing
Towards Crack Arrest Testing Using Miniature Specimens
Determination of Transferable Lower-Bound Fracture Toughness from Small Specimens
Effects of Surface Morphology and Distributed Inclusions on the Low Cycle Fatigue Behavior of Miniaturized Specimens of F82H steel
Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels
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