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SEDL / STP / STP380-EB
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STP380
Flow and Fracture of Metals and Alloys in Nuclear Environments
Committee E10
Pages: 479
Published: 1965
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Table of Contents
Introduction
Weber C.
Mechanisms of Radiation Damage in Reactor Materials
Brinkman J., Wiedersich H.
Mechanisms of Radiation-Induced Mechanical Property Changes
Barnes R.
Irradiation Hardening and Embrittlement in Body-Centered Cubic Transition Metals
Johnson A., Sargent G., Wronski A.
Computer Studies of Neutron Irradiation and Annealing in Finite BCC Iron Specimens
Beeler J.
Effects of Irradiation in Iron and Steels
Eyre B., Harries D.
Low-Temperature Embrittlement of Iron, Iron Alloys, and Steels by Neutron Irradiations
Chow J., McRickard S.
Effect of Irradiation on Bend Transition Temperatures of Molybdenum- and Columbium-Base Alloys
McCoy H., Weir J.
Irradiation Effects on High-Temperature Reactor Structural Metals
Claudson T., Pessl H.
Recovery of Defects in Neutron-Irradiated Tungsten
Moteit J., Smith J.
The Nature and Annealing Behavior of Irradiation Damage in Molybdenum
Eyre B., Roberts A.
Effects of Irradiation in Austenitic Steels and Other High-Temperature Alloys
Harries D., Pfeil P.
The Flow and Fracture Properties of Unirradiated Stainless Steels
Beeghly H.
The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels
Bement A., Hoagland R., Irvin J.
The Effect of Irradiation Temperature on the Post-Irradiation Stress-Strain Behavior of Stainless Steel
Martin W., Weir J.
In-Reactor Stress-Rupture Properties of a 20Cr-25Ni, Columbium-Stabilized Steel
Venard J., Weir J.
New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels
Hawthorne J., Steele L.
In-Depth Embrittlement of a Simulated Pressure Vessel Wall Of A302-B Steel
Serpan C., Steele L.
Strain-Cycle Phenomena In Thin-Wall Tubing
M.
Effects of Irradiation on A302-B Steel Subjected to a Multiaxial Stress Distribution
Flynn P., Trozera T.
In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel
Hawthorne J., Steele L.
Effects of Neutron Irradiation on the Flow and Fracture Behavior of Zircaloy-2
Bement A., Hoagland R., Tobin J.
In-Reactor Creep of Cold-Worked Zircaloy-2
Holmes J., Nyman D., Tobin J., Williams J.
Gas Formation and Compression Fractures in Irradiated Beryllium
J.
The Use of Materials Properties by the Reactor Vessel Designer
Langer B.
The Significance of Recent Developments in Fracture Mechanics In Great Britain In Relation To The Safety Of Reactor Pressure Vessels
Irvine W.
The Important Materials Parameters Affecting the Performance of Nuclear Reactor Pressure Vessels
Wylie R.
Crack Propagation Tests on Zircaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions
Aungst R., Defferding L.
Insurance Aspects of Radiation Damage in Reactor Structures
Catudal F.
Committee: E10
Paper ID: STP380-EB
DOI: 10.1520/STP380-EB
ISBN-EB: 978-0-8031-6007-1
 ASTM International is a member of CrossRef.
0-8031-6161-1
978-0-8031-6161-0
STP380-EB
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