Effects of Radiation on Materials: 22nd Symposium, Issue 1475 |
Contents
Behavior of Irradiated Type 316 Stainless Steels under LowStrainRate Tensile Conditions | 3 |
RadiationInduced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction | 15 |
Low StrainRate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBRII | 32 |
Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel | 41 |
Modeling the Effects of Oversize Solute Additions on RadiationInduced Segregation in Austenitic Stainless Steels | 52 |
PostIrradiation Tensile Behavior and Residual Activity of Several FerriticMartensitic and Austenitic Steels Irradiated in Osiris Reactor at 325C up to 9 ... | 67 |
The Role of Grain Boundary Engineering on the High Temperature Creep of FerriticMartensitic Alloy T91 | 86 |
Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360390C | 99 |
Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209 000 H at 282C | 236 |
Recent Surveillance Data and a Revised Embrittlement Correlation | 245 |
Use of Broken Charpy Vnotch Specimens from a Surveillance Program for Fracture Toughness Determination | 255 |
Dynamic Finite Element Modeling of Fracture in Charpy VNotch Specimens of Weld Material 72W | 262 |
Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys | 274 |
Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper | 285 |
AtomicScale Simulation of Defect Cluster Formation in HighEnergy Displacement Cascades in Zirconium | 299 |
Flow Localization Processes in Austenitic Alloys | 314 |
Development of Fuel Clad Materials for High Burnup Operation of LWR | 111 |
Relation Between Microstructural Evolution and Hardening | 120 |
Radiation Resistance of Advanced FerriticMartensitic Steel HCM12A | 135 |
Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels | 151 |
Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels | 165 |
Radiation and ThermallyInduced Phosphorus InterGranular Segregation in Pressure Vessel Steels | 180 |
Fracture Toughness ThermoElectric Power and Atom Probe Investigations of JRQ Steel in I IA IAR and IARA Conditions | 195 |
Assessment of Neutron IrradiationInduced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel | 212 |
Effects of Neutron Dose Dose Rate and Irradiation Temperature on the Irradiation Embrittlement of a LowCopper Reactor Pressure Vessel Steel | 225 |
Deformation Mechanism Maps of Unirradiated and Irradiated V4Cr4Ti | 328 |
Plutonium238 AlphaDecay Damage Study of a ClassBonded Sodalite Ceramic Waste Form | 347 |
Microstructure Evolution in ZrC Irradiated with Kr Ions | 358 |
Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures | 365 |
CreepFatigue Behavior in High Strength Copper Alloys | 378 |
Tensile Flexural and Shear Properties of Neutron Irradiated SiCSiC Composites with Different FiberMatrix Interfaces | 392 |
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Common terms and phrases
316 stainless steel ADBTT alloys annealing ASTM International ASTM STP atom Atom Probe austenitic behavior carbide Charpy impact Charpy impact test copper correlation creep DBTT decrease dependence dislocation loops dose rate ductility EBR-II Effects of Radiation embrittlement experimental Ferritic flexural fluence fracture toughness grain boundary increase irradiation conditions irradiation hardening irradiation temperature irradiation-induced Journal of Nuclear lattice martensitic martensitic steels matrix measured mechanical properties microstructure modulus neutron fluence neutron flux neutron irradiation Nuclear Materials observed parameters particles PKA energy point defect precipitates precracked Pressure Vessel Steels Radiation on Materials Reactor Pressure Vessel room temperature RPV steels segregation shear shown in Fig shows SIA clusters simulation specimens stainless steels steel irradiated strain rate stress relaxation Table tensile tests test temperature thermal aging uniform elongation unirradiated vacancy clusters volume fraction VVER weld West Conshohocken yield strength yield stress