Effects of Radiation on Materials: 11th International SymposiumH. R. Brager, J. S. Perrin ASTM International, 1982 - 1225 pages |
Table des matières
Introduction | 1 |
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 |
An InReactor Creep Correlation for 20 Cold Worked AISI 316 | 108 |
Analysis of the High Fluence Creep Behavior of Two Precipitation | 122 |
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 Austenitic Superalloys | 619 |
Mechanical Properties of Highly Irradiated 20 Percent Cold Worked | 636 |
NickelDoped Ferritic Martensitic Steels for Fusion Reactor | 648 |
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 |
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 |
Effects of Temperature and Strain Rate on the Low Cycle Fatigue | 665 |
Deformation of Microstructure 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 |
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 |
Autres éditions - Tout afficher
Effects of Radiation on Materials: Proceedings of the Eleventh International ... H. R. Brager,J. S. Perrin Aucun aperçu disponible - 1982 |
Expressions et termes fréquents
316 stainless steel AISI alloys annealed atoms austenitic behavior beryllium calculated capsule cavity Charpy cladding cold-worked composition copper core creep rate curves damage rate decrease dependence diameter dislocation density dislocation loops dose ductility EBR-II Effects of Radiation electron embrittlement energy equation experimental ferritic fluence flux fracture toughness grain boundaries helium in-reactor creep Inconel increase ion bombardment irradiated condition irradiation creep irradiation temperature Journal of Nuclear martensite matrix measured microstructure monazite n/cm² neutron fluence neutron irradiation nickel nickel content notch Nucl number density observed parameter particles peak phase plate precipitates preinjected radiation hardening Radiation on Materials range region samples shown in Figure silicon Society for Testing strain rate strength stress structure submerged arc welding swelling rate Table test temperature Testing and Materials thermal transmission electron microscopy tube Type 316 stainless unirradiated values void swelling weld metal yield strength Zircaloy
Fréquemment cités
Page 1136 - Effects of Radiation on Materials: Eleventh Conference, ASTM STP 782. HR Brager and JS Perrin, Eds., American Society for Testing and [8] Gelles, DS in Effects of Radiation on Materials: Tenth Conference, ASTM STP 725, D.