Effects of Radiation on Materials: 20th International Symposium

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Stan T. Rosinski
ASTM International, 2001 - Technology & Engineering - 879 pages
 

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Contents

A MechanisticallyBased Model of Irradiation Damage in Low Alloy Steel Submerged
8
Vessel Investigation Program of CHOOZ A PWR Reactor after Shutdownc
28
Development of Reconstitution Technology for Surveillance Specimens in Japan Power
42
Master Curve Characterization of Irradiation Embrittlement Using Standard and 13
53
Radiation Damage Assessment by the Use of Dynamic Toughness Measurements on Pre
68
Comparison of Transition Temperature Shifts Between Static Fracture Toughness
79
Yield and Toughness Transition Predictions for Irradiated Steels Based on Dislocation
97
Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steels
125
Tensile Properties of 12 ColdWorked Type 316 Stainless Steel Irradiated in EBRII
469
Irradiation Creep Deformation of Modified 316 and 15Cr20Ni Base Austenitic Fuel
487
Behavior of Different Austenitic Stainless Steels Conventional Reduced Activation
500
Effect of Specimen Size on Fatigue Properties of Reduced Activation FerriticMartensitic
535
Correlation Between Creep Properties and Microstructure of Reduced Activation
546
Comparison of Thermal Creep and Irradiation Creep of HT9 Pressurized Tubes at Test
557
Examination of 304L Stainless Steel to 6061T6 Aluminum Inertia Welded Transition
571
Microstrucural Alteration of Structural Alloys by Low Temperature Irradiation with High
588

Review of Phosphorous Segregation and Intergranular Embrittlement in Reactor Pressure
151
Modeling of Phosphorous Accumulation on Grain Boundaries in Iron Alloys Under
174
An Evaluation of ThroughThickness Changes in Primary Damage Production
204
Hardness and Microstructure Changes with Thermal Annealing of NeutronIrradiated
218
Effects of Copper Concentration and Neutron Flux on Irradiation Hardening
237
Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron
247
Microstructural Evolution in High Nickel Submerged Arc Weldsj m hyde d ellis
262
An Evaluation of the Effect of Radiation Environment on Linde 80 Reactor Vessel
290
Reirradiation Response Rate of a HighCopper Reactor Pressure Vessel Welds k
302
Relation Between Resistivity and Mechanical Properties in Heat Affected Zone
315
Fracture Toughness and Tensile Properties of Irradiated Reactor Pressure Vessel
328
True Characteristics of Strength and Ductility for NeutronIrradiated Metals
343
Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following
356
Composition Effects on the Radiation Embrittlement of Iron AlloysJ bohmert
383
The Determination of Bias Factor Stress Dependence from Experimental Data
401
Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts
413
RadiationInduced Segregation and Void Swelling in 304 Stainless Steelt r allen
427
Effect of Irradiation Environment of Fast Reactors Fuel Elements on Void Swelling in
443
The Swelling Dependence of Cold Worked 16Cr15Ni2MolMn Steel on Neutron
457
Retention of Very High Levels of Helium and Hydrogen Generated in Various Structural
610
The Influence of High Energy Proton Irradiation on the Corrosion of Materials
631
The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials
644
HighEnergy Spallation Neutron Effects on the Tensile Properties of Materials for
660
Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels
673
Dimensional Characteristics of Displacement Cascades in Austenitic Steels under
694
On the a+77Phase Boundary in Nickel and in Manganese Containing Stainless Steel
704
Effect of Nickel on Irradiation Hardening and Microstructure Evolution of Proton
722
Effect of Final Irradiation Temperature and Frequency of Irradiation Temperature
736
Hardening of Vanadium Doped with Nitrogen by Heavy Ion Irradiation and Post
746
Hydrogen and Helium Gas Formation and their Release Kinetics in Tungsten Rods after
762
The Influence of Temperature Fluence Dose Rate and Helium Production on Defect
775
Microstuctural Stability of SiCSiC Composites under DualBeam Ion Irradiation
785
Molecular Dynamics Simulation of Radiation Damage Production in Cubic Silicon
799
Influence of the Reactor and Cyclotron Irradiation on Energy Transformation during
813
IrradiationInduced Amorphization and its Recovery Behavior in ColdRolled and Aged
825
Effect of Mass and Energy on Preferential Amorphization in Polycrystalline Silicon Film
836
Crack Growth Resistance of Irradiated Zr2 5Nb Pressure Tube Material at
846
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