|
|
|
SEDL / STP / STP683-EB
 |
---->
STP683
Effects of Radiation on Structural Materials
Sprague JA, Kramer David
Pages: 675
Published: 1979
Other books in this series
|
|
This volume covers six subject areas: microstructure, fracture of thermal reactor materials, primary damage production and irradiation creep simulation, dosimetry and damage function analysis, mechanical properties and creep.
Table of Contents
Introduction
Sprague J.
Summary
Determination of the Nature of Neutron Irradiation-Induced Dislocation Loops in Magnesium Using Electron Irradiation in the Transmission Electron Microscope
Wolfenden A.
Radiation Effects on Molybdenum Alloys Bombarded by Electrons in a High-Voltage Electron Microscope
Igata N., Itadani K., Kohyama A.
Microstructural Development During Low-Dose Irradiation
Hall B., Potter D.
Neutron Irradiation-Induced Defect Structures in Zirconium
Blake R., Farrell K., Jostsons A., Kelly P.
Irradiation Growth in Zirconium and Its Alloys
Northwood D.
Dependence of Cavity Nucleation Density Upon Gas Implantation Rate and Its Importance in Dual-Beam Irradiation Conditions
Bullough R., Hayns M., Wood M.
Response of Inconel 600 to Simulated Fusion Reactor Irradiation
Wiffen F.
Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium-Base Alloys
Michel D., Smith H.
Effects of Bombarding Ions on the Void Swelling Profile in Nickel
Kulcinski G., Smith H., Whitley J., Wilkes P.
Development of Physically Based Void Swelling Equations for Engineering and Design Use
Bullough R., Hayns M.
A Reassessment of the Role of Stress in Development of Radiation-Induced Microstructure
Brager H., Garner F., Wolfer W.
Radiation-Induced Segregation in Nickel-Silicon Alloys
Okamoto P., Potter D., Rehn L., Wiedersich H.
An Example of Precipitate Stability in Reactor-Irradiated Nimonic PE16
Gelles D.
Dependence of Void Formation on Phase Stability in Neutron-Irradiated Type 316 Stainless Steel
Brager H., Garner F.
Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for Radiation Resistance
Byrne S., Hawthorne J., Koziol J.
An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel Materials
Byrne S., Varsik J.
Irradiation Behavior of Nickel-Chromium-Molybdenum Type Weld Metal
Gerscha A., Klausnitzer E., Leitz C.
Exploratory Investigations of Cyclic Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits
Hawthorne J., Loss F., Watson H.
Effect and Possibilities of Irradiation Results Error Correction (Demonstrated on the Results of the IAEA Coordinated Program)
Nagel G.
Fracture Toughness of Irradiated Beryllium
Beeston J.
Irradiation Creep and Growth in Zirconium During Proton Bombardment
Faulkner D., McElroy R.
Radiation Damage Effects in 16-MeV Proton and 14-MeV Neutron Irradiated Nickel and Niobium
Bradley E., Jones R., Styris D.
Helium Production in Fast Breeder Reactor Out-of-Core Structural Components
Simons R.
Radiation Damage Function Analysis
Gold R., Lippincott E., McElroy W., Simons R.
Solid-State Track Recorder Materials for Use in Light-Water-Reactor Pressure Vessel Surveillance Exposures
Gold R., Roberts J., Ruddy F.
Microstructure and Tensile Properties of Heavily Irradiated 1100-0 Aluminum
Farrell K., Richt A.
Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions
Farrell K., King R.
Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel
Cannon N., Fish R., Wire G.
Low-Cycle Fatigue of Three Irradiated and Unirradiated Vanstar Alloys
Korth G., Schmunk R.
Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1.4948
de Vries M., Elej L., Staal H., van der Schaaf B.
Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor Systems
Brinkman C., Grossbeck M., Liu K.
Fracture Toughness of Irradiated AISI 304 and 316L Stainless Steels
Dufresne J., Henry B., Larsson H.
Fracture Toughness of Irradiated Nimonic PE16 at High Temperatures
Jones R., Nicholson R.
Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic Loading
Albertini C., Del Grande A., Montagnani M.
Effects of Irradiation Temperature, Fluence, and Heating Rate on Postirradiation Flow Properties of Cladding Under Simulated Temperature Transient Heating and Deformation Conditions
Cannon N., Duncan D.
Effects of Irradiation Creep on Ex-Reactor Mechanical Properties
Duncan D.
Formulation of Constitutive Laws for Deformation During Irradiation
Wolfer W.
Irradiation Creep in Bending of Cold-Worked AISI 316 Stainless Steel at Low Neutron Fluence
Appleby W., Marshall J., McSherry A., Patel M.
A Comparison of Fuel Pin Deformations with Pressurized Tube Creep Tests
Gilbert E., Lovell A., Taylor J.
Reduction of Irradiation-Induced Creep by Point-Defect Trapping
Mansur L., Wolfer W.
Irradiation Creep Due to Stress-Induced Preferred Absorption of Point Defects in Zirconium Single Crystals
Woo C.
In-Reactor Deformation and Fracture of Austenitic Stainless Steels
Bloom E., Wolfer W.
Index
Committee: E10
Paper ID: STP683-EB
DOI: 10.1520/STP683-EB
ISBN-EB: 978-0-8031-5551-0
 ASTM International is a member of CrossRef.
0-8031-0327-1
978-0-8031-0327-6
STP683-EB
|
