Effects of Radiation on Materials |
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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Common terms and phrases
addition aged AISI alloys analysis annealed appears ASTM behavior calculated capsule cavity Charpy cladding cold-worked compared component composition concentration consistent contained copper core curves damage decrease defect density dependence determined Development diameter dislocation distribution dose effect electron elements embrittlement energy equation examined experiment experimental Figure fluence formation fracture fuel given grain boundaries growth heat helium higher increase indicated influence initial irradiation creep irradiation temperature loops lower Materials matrix measured mechanism metal microstructure neutron neutron irradiation nickel Nuclear observed obtained occurs parameter phase plate precipitates predicted present pressure produced properties Radiation range reactor reduction REFERENCE region relatively reported shift shown shows silicon similar sinks solution specimens stainless steel strain strength stress structure swelling Table temperature thermal tube unirradiated values vessel void weld