Effects of Radiation on Materials: 15th International Symposium

Front Cover
ASTM International, 1992 - Electronic book - 1323 pages
Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization
 

What people are saying - Write a review

We haven't found any reviews in the usual places.

Contents

The Design and Performance of HighTemperature Irradiation Capsules
12
InService Evaluation of French Pressurized Water Reactor Vessel Steel
22
Neutron Irradiation Embrittlement of Pressure Vessel Materials in Spanish
50
Evaluation of Tarapur Atomic Power Station Pressure Vessel Surveillance
56
Mechanical Testing of Civil Advanced GasCooled Reactor Tie Bars
64
Reconstituted Impact Specimens with Small Insertsegon n klausnitzer
76
Investigations of Gundremmingen RPV Archive Material Irradiated in Light
93
Evolution of the Microstructure of PWR Pressure Vessel Steels from the CHOOZ
117
Positron Lifetime Studies of Helium Bubble Kinetics in AlphaIrradiated
875
Relationship of Microstructure and Tensile Properties for NeutronIrradiated
885
Vanadium Alloys with Improved Resistance to Helium Embrittlement
897
Effect of Helium and dpas on Tensile Properties of V5Ti and V3TilSi
915
Large Swelling Observed in a V5atoFe Alloy after Irradiation in FFTF
928
A Contribution to the Phase Diagram of FeMnCr AlloysWolfgang schule
945
Microstructural Examination of FeCrMn Alloys after Charged Particle
958
The Effects of Nickel on Microstructural Development and Microchemical
969

A Theoretical Model of Accelerated Irradiation Creep at Low Temperatures
517
Dislocation Core Microstructure and Its Effect on Irradiation Creep
530
Irradiation Creep by GlideInduced Transient Absorptionalan d brailsford
540
Diffusion Growth Rate of Macrodefects in Ensemblesvitaly v slyozov
556
An Account of PointDefect Recombination in the Theory of Void Swelling
569
Spatial SelfOrganization of a Void System in Irradiated Metals
583
AutoOscillation Process in Impure Crystals under Irradiationp a selishchev
594
RadiationInduced Segregation in 20Cr25NiNb Stainless Steel
603
IrradiationInduced Microchemical Effects and IASCC Initiation
621
Interfacial Segregation in Fast Reactor Irradiated 12 Chromium Martensitic
633
The Effect of Neutron Irradiation on Segregation to Grain Boundaries in Nimonic
645
Microstructural Characterization of Irradiated Nimonic PE16
667
Segregation of Tin in Zircaloy2 under Proton IrradiationArthur t motta
689
XRay Analysis of the Surface Alloy Formed by HighDose Implantation of Iron
703
RadiationModified Phase Diagrams of Binary AlloysAlexander s bakai
709
The Defect Structure of Ion and Neutron Irradiated YBa2Cu307j Single
732
The Effect of Crystal Orientation on Damage Accumulation in Chromium
740
Dislocation Loop Formation in IonIrradiated Polycrystalline Spinel
749
Radiation Damage in Fusion Window Materials Studied by Thermal
764
Electrical Conductivity of Single Crystal aAlumina under Neutron and 7Ray
776
Effects of Neutron Irradiation on Ceramics FiberReinforced Composites
785
Mechanistic Interpretation of an Observed FissionRate Dependence of Low
797
A Brief Review of RadiationInduced Cavity Swelling and Hardening in Copper
811
Unusual Tensile and Fracture Behavior of Pure Copper at High Levels of Neutron
833
Tensile Behavior of Cu5Ni and Various PrecipitationStrengthened Copper Alloys
846
Mechanical Property Changes and Microstructures of DispersionStrengthened
854
Ion Irradiation Effects on a Martensitic Stainless Steel Designed for Reduced
979
The Effect of Phosphorus on the RadiationInduced Microstructure of Stabilized
994
The Influence of Nickel Content on Microstructures of FeCrNi Austenitk
1015
The Behavior of IrradiationProduced Dislocation Loops under External Stress
1034
Simulation Study of LowTemperature Irradiation and a LOCA and the Resulting
1051
Surface Modification of Austenitic 304 Stainless Steel by N2+ and 11B+
1061
Transient and Static Mechanical Properties of D9 Fuel Pin Cladding and Duct
1071
Effect of Hold Time and Frequency on the Fatigue Crack Growth Rate
1083
Comparison of SmallScale Bending and Axial Fatigue Specimensgopal r
1095
Characterization of 316L SteelWelded Joints Irradiated Between 15 and 41 dpa
1103
Effect of Microalloying with Boron and RareEarth Metals on Swelling
1122
Comparison of the Effects of LongTerm Thermal Aging and HFIR Irradiation
1135
Radiation Damage Studies of the 10 to 13 ChromiumContaining Steels
1157
A Comparison of Heavy IonIrradiated Ferritic and Austeniric Steels in the Early
1167
The Effect of Neutron Irradiation on the Microstructure and Tensile Properties
1180
Precipitation Evolution in HT9 Steel under Thermal Aging and Stress Rupture
1190
Behavior under Neutron Irradiation of the 1515Ti and EM10 Steels Used
1209
Postirradiation Strength and Deformation of Ferritic FeCr Binary Alloys
1234
Ductility and Hardening of NeutronIrradiated FeCr and FeCrNi Steels
1243
Irradiation Effects on Impact Behavior of 12CrlMoVW and 2CrlMo Steels
1256
Fracture Toughness and Tensile Properties of Alloy HT9 in Thin Sections under
1267
Evaluation of Irradiation Embrittlement of 2CrlMo Steel in Terms of Elastic
1287
Effect of Neutron Irradiation on the Mechanical Properties of Microalloyed Steel
1304
Indexes
1311
Copyright

Common terms and phrases

Bibliographic information