Effects of Radiation on Materials

Front Cover
ASTM International, 2004 - Technology & Engineering - 770 pages
 

Contents

Properties of 20 ColdWorked 316 Stainless Steel Irradiated at Low Dose Rate
3
Study on Ductile Fracture Strain and Fracture Toughness of Irradiated Austenitic Stainless Steels
15
Investigation of Microstructure and Mechanical Properties of 18Cr10NiTi Steel Irradiated in the Core of V VER1000 Reactor
32
Influence of Oversized Solute Additions on RadiationInduced Microstructure and Microchemistry in Austenitic Stainless Steel
46
Solute Addition Effect for Fe15Cr20Ni Austenitic Steels Irradiated in Joyo
56
The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels
66
The Role of Fine Defect Clusters in IrradiationAssisted Stress Corrosion Cracking of ProtonIrradiated 304 Stainless Steel
78
The Effect of Hardening Source in Proton IrradiationAssisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel
92
Incubation Period for Void Swelling and Its Dependence on Temperature Dose Rate and Dislocation Structure Evolution
418
Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWRRelevant Displacement Rates
429
Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr15Ni2Mo1Mn Cladding Irradiated in BN600
446
Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling
454
Irradiation Creep and Swelling of Russian FerriticMartensitic Steels Irradiated to Very High Exposures in the BN350 Fast Reactor at 305335C
468
Kinetics of Helium Bubble Formation in Nuclear and Structural Materials
479
Bubble Microstructures in Helium Injected Palladium Foils
492
Fatigue Response and Life Prediction of Selected Reactor Materials
502

Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels
105
Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld
123
On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences
138
Irradiation and PostAnnealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ
149
Dependence of Reembrittlement Rate After Annealing on the Copper Nickel and Phosphorus Contents in Model Alloys
164
Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other LowAlloy Steels
179
Composition and Flux Effects
194
Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds
208
Critical Review of ThroughWall Attenuation of Mechanical Properties in RPV Steels
221
A MechanisticallyGuided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment
247
Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region
266
Master Curve of Irradiated JRQ Material
277
Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity
289
The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness
300
A Statistical Analysis of the Effect of Neutron Irradiation Dose and Dose Spectrum on Changes of Charpy Impact Energy for CMn Steels
311
The Effect of Neutron Flux on Radiationinduced Embrittlement in Reactor Pressure Vessel Steels
326
Hardening Mechanisms in FerriticMartensitic Steels
341
Effects of Copper Content on the Tensile Properties of IronCopper Alloys
352
Irradiation Hardening and Microstructural Evolution in FeCu Model Alloys
365
Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe9Cr2W 025V Steel
376
Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation
391
Examination of Postirradiation Deformation Microstructures in F82H
401
Fracture Toughness Characterization of Irradiated F82H in the Transition Region
408
Detection of RadiationEnhanced Diffusion by Means of NeutronIrradiated Diffusion Couples of FeCrNi System
516
Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures
529
The Influence of Prelrradiation Heat Treatments on Thermal NonEquilibrium and RadiationInduced Segregation Behavior in Model Austenitic Stainl...
540
laterGranular Phosphorus Segregation in Ferritic Steels
553
Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels
565
The Modeling of RadiationInduced Phosphorus Segregation at Point Defect Sinks in Dilute FeP Alloys
579
Irradiation Induced VacancyCu Aggregations in FeCu Model Alloys of Reactor Pressure Vessel Steels Studied by Positron Annihilation
590
Heavy Ion Fiuence Measurements Based on Radiation Effects Generated in CTA Foils
604
Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture
612
Revisiting the Use of SiC as a Post Irradiation Temperature Monitor
623
New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data
634
Mechanical and Structural Property Changes of Monolithic SiC and Advanced SiCSiC Composites due to Low Temperature He+lon Irradiation and P...
655
Precipitation and Amorphization in Boron Carbide Irradiated by High Energy Helium Ions
670
Effects of Pu Decay on a Sodalite Based Ceramic Waste Form
680
Changes in Mechanical Properties of HighPurity V4Cr4Ti Si AI Y Alloys after Neutron Irradiation at Relatively Low Temperatures
692
Creep Deformation in V4Cr4Ti in a LowOxygen Lithium Environment
702
Varying Temperature Irradiation Effects of V4Cr4Ti Alloy with Small Addition of Si Ai and Y
714
Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 dpa
727
Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy4
741
Microstructure Response in Copper and Copper Alloys Irradiated with Fission Neutrons with Controlled Temperature Variations
753
Author Index
763
Subject Index
767

Other editions - View all

Common terms and phrases