Effects of Radiation on Materials: 22nd Symposium, Issue 1475

Front Cover
ASTM International, 2006 - Materials - 408 pages
 

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Contents

RadiationInduced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated
15
Low StrainRate Microstructural Deformation Behavior in 316 Stainless Steel
32
Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel
41
Modeling the Effects of Oversize Solute Additions on RadiationInduced Segregation
52
PostIrradiation Tensile Behavior and Residual Activity of Several FerriticMartensitic
67
The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic
86
Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360390C
99
Development of Fuel Clad Materials for High Burnup Operation
111
Mechanical Property Changes in Reactor Vessel Materials Thermally Aged
236
Recent Surveillance Data and a Revised Embrittlement CorrelationW L SERVER
245
Use of Broken Charpy Vnotch Specimens from a Surveillance Program for Fracture
255
Dynamic Finite Element Modeling of Fracture in Charpy VNotch Specimens of Weld
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
285
AtomicScale Simulation of Defect Cluster Formation in HighEnergy Displacement
299
Flow Localization Processes in Austenitic AlloysX WU X PAN M LI
314

Relation
120
Radiation Resistance of Advanced FerriticMartensitic Steel HCM12AT R ALLEN
135
Microstructural and Mechanical Characterization of Radiation Effects in Model
151
Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels
165
Radiation and ThermallyInduced Phosphorus InterGranular Segregation
180
Fracture Toughness ThermoElectric Power and Atom Probe Investigations of
195
Assessment of Neutron IrradiationInduced Grain Boundary Embrittlement
212
Effects of Neutron Dose Dose Rate and Irradiation Temperature on the Irradiation
225
Deformation Mechanism Maps of Unirradiated and Irradiated V4Cr4Ti
328
Plutonium238 AlphaDecay Damage Study of a ClassBonded Sodalite Ceramic
347
Microstructure Evolution in ZrC Irradiated with Kr IonsJ GAN M K MEYER
358
Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated
365
CreepFatigue Behavior in High Strength Copper AlloysJ F STUBBINS AND M LI
378
Tensile Flexural and Shear Properties of Neutron Irradiated SiCSiC Composites
392
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