Digital Library / Topics / Nuclear, Solar, and Geothermal Energy / Recent 25 JAI

• Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel
• Neutron Response Function for BC-523A Scintillation Detector in the Energy Range 0.5 MeV to 20 MeV
• Surveillance of the Fracture Behavior of Zircaloy-4 Welds Using the Small Punch Test
• Application of Digital Marker Extensometry to Determine the True Stress-Strain Behavior of Irradiated Metals and Alloys
• Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region
• Fracture Toughness Evaluation of Eurofer97 by Testing Small Specimens
• Track Detector Measurements in RPV of WWER-1000 Mock-Up in the LR-0 Reactor
• Crack Arrest Testing Using Small Wide Plate SE(T) Specimens
• Using Subsize Impact Bend Specimens for Estimation of Irradiation and Re-Irradiation Embrittlement of VVER RPV Steels
• Application of Subsize Specimens for Irradiation Embrittlement Monitoring of VVER-440/213 RPV Steels
• Miniature Compact Tension Specimens for Upper Shelf Fracture Toughness Measurements on RPV Steels
• Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall
• Use of KLST-Type Miniature Charpy Specimens for Measuring Dynamic Fracture Toughness under Impact Loading Rates
• Microstructural Features in Aged Erbium Tritide Films
• Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Pressure Vessel MonitoringReview of Some REDOS Project Results
• Specimen Size Limitations in Curve TestingStandards Versus Reality
• Master Integrated Reactor Vessel Surveillance Program
• The Feasibility of Using a Risk-informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves
• Kinetics of the Migration and Clustering of Extrinsic Gas in bcc Metals
• Grain Growth in Nanocrystalline Metal Thin Films under Ion-Beam Irradiation
• DD Simulations of Dislocation-Crack Interaction During Fatigue
• Radiation Embrittlement of CrNiMo and CrMo RPV Steels
• Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels
• Strain Hardening During Mechanical Twinning and Dislocation Channeling in Irradiated 316 Stainless Steels
• Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material
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