Effects of Radiation on Materials

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ASTM International, 1981
 

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Contents

The Swelling of Solution Annealed 316 Cladding in Rapsodie
5
Effects of Radiation on Materials 10th Conference STP 725 1981
16
The Swelling Behavior of 20 CW 316 Stainless Steel Cladding
17
Interdependence of InPile Creep and Void Swelling in Ti and
30
Initial Results of Swelling and Irradiation Creep Interaction
44
Creep and Swelling of Type 348 Stainless Steel at Temperatures
71
Effect of Preinjected Helium on Swelling and Microstructure
92
Effects of Radiation on Substructure and Mechanical Properties of Metals
107
NickelDoped Ferritic Martensitic Steels for Fusion Reactor
648
Effects of Temperature and Strain Rate on the Low Cycle Fatigue
665
Deformation of MIcrostracture Developed During Fatigue Crack
690
Effects of Fast Neutron Irradiation on the Fracture Behavior
701
Fatigue Crack Growth of LowFluence NeutronIrradiated Stainless
720
The Influence of Neutron Irradiation on the Properties of Beryllium
735
A Comparison of TransientHeating Burst Test Results of Unirra
749
Effects of Neutron Irradiation on the Mechanical Properties
765

An InReactor Creep Correlation for 20 Cold Worked AISI 316
108
Analysis of the High Fluence Creep Behavior of Two Precipitation
122
The Influence of Cold Work Level Solute and Helium Content
152
Precipitation in Irradiated and Unirradiated Austenitic Steels
166
Relationship Between Phase Development and Swelling of AISI 316
186
Microstructural Stability of Fast Reactor Irradiated 1012Cr
207
Dislocation Substructure in Zirconium Alloys Irradiated in EBRII
234
The Effect of Preimplanted Helium on the Microstructure
251
Swelling in Neutron Irradiated Titanium Alloysd t peterson
260
The Effect of Matrix Cavities and Cavity Density on the Formation
275
History Dependence and Consequences of the Microchemical
295
Influence of Dose and Dose Rate on the Microstructure of Solution
310
Microstructure and Tensile Properties of NeutronIrradiated
325
The Influence of Neutron Exposure Chemical Composition
343
Irradiation Effects on Structural Alloys for Nuclear Reactor Applications
373
Significance of Nickel and Copper Content to Radiation Sensitivity
375
Comparative Irradiation Study of RPV Steel Weld Metalsc leitz
412
Evaluation of Advanced Reactor Pressure Vessel Steels Under
433
Analysis of Fracture Surfaces of Reactor PressureVessel Steels
464
Analytic Predictions of Embrittlement of A533B Pressure Vessel
492
Kinetics of Annealing of Irradiated Surveillance Pressure Vessel
505
Irradiation Experiments in the Testing Nuclear Power Plant VAK
520
Effects of Neutron Irradiation and Temperature on High Strain
550
A Single Specimen Method for Determining Upper Shelf Fracture
563
Preparation of Reconstituted Charpy VNotch Impact Specimens
582
Low Dose Irradiation Effects on HeattoHeat Variation of Type
597
Irradiation Embrittlement in Some Austenltic Superalloys
619
Mechanical Properties of Highly Irradiated 20 Percent Cold Worked
636
On the Possibility of Using Amorphous Metals in HighRadiation
779
Annealing of Radiation Damaged Monazitek a gowda
799
Void Swelling of Ferritic Alloys Bombarded with Nickel Ions
809
Void Swelling and Phase Stability in Different Heats of ColdDrawn
824
Irradiation Creep of Dilute Nickel Alloyst atkins
841
Optimization of Precipitation Hardened FeNICr Alloys Using
856
Ion Damage in 316 Stainless Steel Over a Broad Dose Range
885
Surface Segregation in Concentrated NiCu Alloys Under Irradiation
895
The Effect of Nitrogen on Void Swelling of Stainless Steel
906
Mechanical Properties of 800MeV ProtonIrradiated Metals
917
Damage Profile in IonBombarded Nickel and Stainless Steel
927
The Effect of Pulse Irradiation on Void Swelling of 316 Stainless
941
Comparison of Neutron and HeavyIon Damage in a Stable Austen
953
Defect Production Rates by Electrons Ions and Neutrons in Cubic
963
Kinetics of RadiationInduced Segregation in Ternary Alloys
985
Effect of RadiationInduced Segregation on Void Nucleation
1008
On RadiationInduced Segregation and the Compositional Depen
1023
Calculation of Cavity Nucleation Under Irradiation with Continuous
1042
Hardening of Irradiated Alloys Due to the Simultaneous Formation
1054
A Model for the Evolution of Network Dislocation Density
1073
Asymmetric DislocationPointDefect Interactions and the Modeling
1088
Influence on Commercial Nuclear Power Development
1123
European Fusion Materials Programj darvas
1140
U S Fusion Reactor Materials DevelopmentR w conn
1159
PhenixRapsodie The Core Materials Storyi m dupuoy
1179
U K Fast Reactor Materials Programd r harries
1197
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