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STP611 Irradiation Effects on The Microstructure and Properties of Metals Shober FR Pages: 483 Published: 1976 Format: PDF (9.5M) Price: $126  [Download Now]

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Table of Contents

Introduction
Shober F.

Effects of Prior Stress History on Irradiation-Induced Creep
Wire G.

Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models
Foster J.

Dynamic Strain-Aging and Neutron Irradiation in Mild Steel
Murty K., Hall E.

Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel
Garr K., Pard A.

Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel
Fish R., Watrous J.

Mechanical Properties of Fast Reactor Fuel Cladding for Transient Analysis
Hunter C., Johnson G.

Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel
Fish R., Hunter C.

Effects of Neutron Irradiation on Microstructure and Mechanical Properties of Nimonic PE-16
Sklad P., Clausing R., Bloom E.

Irradiation and Thermal Effects on the Tensile Properties of Inconel-718
Ward A., Steichen J., Knecht R.

Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions
Lowry L., Perrin J., Bauer A.

Neutron Energy Dependent Damage Functions for Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel
Simons R.

Swelling Simulation Studies of Type 316 Stainless Steel
Ellis J., Appleby W., Lauritzen T.

Development and Evaluation of a Stress-Free Swelling Correlation for 20 Percent Cold-Worked Type 316 Stainless Steel
Garner F., Laidler J., Guthrie G.

Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment
Smidt F., Malmberg P., Sprague J., Westmoreland J.

Observation of Defect Clusters of Columbium and Columbium Alloys In Situ Irradiated Under a High-Voltage Electron Microscope
Igata N., Watari F., Murakami H.

Void Growth Suppression by Dislocation Impurity Atmospheres
Weertman J., Green W.

Dependence of Void Swelling on the Electron Vacancy Concentration
Watkin J.

Microstructure and Mechanisms of Ion-Simulated Irradiation-Induced Creep of Nickel
Michel D., Hendrick P., Pieper A.

Effects of Interstitial Solutes on the Microstructures of Self-Ion Irradiated Vanadium
Agarwal S., Potter D., Taylor A.

Swelling and Gamma-Prime Particle Stability of Ion-Bombarded Iron-Chromium-Nickel Alloys
Bleiberg M., Bajaj R., Baron I., Chang A., Chickering R., Diamond S.

Effect of Ion Irradiation on the Microstructure of an Iron-Nickel-Chromium Alloy
Sprague J., Smidt F., Westmoreland J., Malmberg P.

Microstructural Changes in Ion-Irradiated Commercial Alloys
Bell W., Lauritzen T., Darlin E., Warner R.

Nickel-Ion Damage in a Precipitation-Hardened Nickel-Aluminum
Kirchner L., Smidt F., Kulcinski G., Sprague J., Westmoreland J.

Fracture Mechanics Characterization of the Trino Reactor Vessel Material
Mager T., Davidson J., Galliani M.

Evaluation of the Maine Yankee Reactor Beltline Materials
Wullaert R., Sheckherd J., Smith R.

Evaluation of the Effect of Chemical Composition on the Irradiation Sensitivity of Reactor Vessel Weld Metal
Biemiller E., Byrne S.

Annealing of Irradiation Damage in High-Copper Ferritic Steels
Spitznagel J., Shogan R., Phillips J.

Displacement Spike Annealing in Iron at Reactor Temperatures
Beeler J., Beeler M.

Neutron Displacement Damage Cross Sections for Structural Metals
Doran D., Graves N.

Index


Committee: E10
Paper ID: STP611-EB
DOI: 10.1520/STP611-EB
ISBN-EB: 978-0-8031-5543-5

ASTM International is a member of CrossRef.
0-8031-0388-3
978-0-8031-0388-7
STP611-EB