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SEDL / STP / STP426-EB
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STP426
Effects of Radiation on Structural Metals
Committee E-10
Pages: 706
Published: 1967
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Table of Contents
Introduction
Rice W.
General Discussion
Effect of Nitrogen on the Mechanical Properties of Neutron-Irradiated Pure Iron
Castagna M., Ferro A., Rossi F., Sebille J.
Effects of Heat-Treatment and Irradiation on the High Temperature Tensile Properties of Austenitic Stainless Steels
Harries D., Roberts A.
Engineering Significance of Ferrite Grain Size on the Radiation Sensitivity of Pressure Vessel Steels
Gordon G., Klepfer H.
Effects of Neutron Irradiation on the Elevated Temperature Mechanical Properties of Nickel-Base and Refractory Metal Alloys
Claudson T.
Irradiation Effects on the Mechanical Properties of Vanadium-Base Alloys
Böhm H., Dienst W., Hauck H., Laue H.
Irradiation Damage in Mild Steel: A Comparison of Crack Arrest Test and Charpy Criteria and Influence of Neutron Spectrum
Cowan A., Fearnehough G., Gillies J., Lees G.
Gas Release and Compression Properties in Beryllium Irradiated at 600 and 750 C
Beeston J.
Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance
Carter J., Williams J.
An Electron Microscope Investigation of High-Temperature Embrittlement of Irradiated Stainless Steels
Carpenter G., Merrick H., Nicholson R., Rowcliffe A.
Review of Swedish Work on Irradiation Effects in Canning and Core Support Materials
Grounes M.
Review of Swedish Work on Irradiation Effects in Pressure Vessel Steels and on Significance of Data Obtained
Grounes M.
An Evaluation of Radiation Damage to Reactor Vessel Steels Using Both Transition Temperature and Fracture Mechanics Approaches
Hazelton W., Landerman E., Yanichko S.
Nature of Radiation Damage to Engineering Properties of Various Stainless Steel Alloys
Bernent A., Irvin J.
Applications of Fracture Mechanics in Evaluating Initiation and Propagation of Brittle Fracture in Reactor Structural Components
Bernent A., Hoagland R., Rowe R.
Neutron Irradiation Embrittlement of Several Higher Strength Steels
Gray R., Hawthorne J., Steele L.
Implications of Embrittlement During the Life of a Zirconium Pressure Tube Reactor
Nichols R., Watkins B.
Properties of Irradiated Materials Needed for the Design of Reactor Vessels. Part I, Water Cooled Reactors
McLaughlin D.
Fatigue Properties of Irradiated Pressure Vessel Steels
Gibbons W., Mikoleit A., O'Donnell W.
Solutions to the Problems of High-Temperature Irradiation Embrittlement
Martin W., Weir J.
Improved Postirradiation Tensile and Stress-Rupture Properties of Hastelloy X-280
Levy I., Wheeler K.
Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel
Kangilaski M., Shober F.
Effects of Neutron Irradiation on Creep-Rupture Properties of W-25RE Alloy
Kingsbury F., Moteff J.
Metallurgical Variables as Possible Factors Controlling Irradiation Response of Structural Steels
Hawthorne J., Steele L.
Dose Rate, Annealing, and Stress Relaxation Studies of Radiation Hardening in Iron
Hinkle N., Ohr S., Wechsler M.
Damaging Neutron Exposure Criteria for Evaluating the Embrittlement of Reactor Pressure Vessel Steels in Different Neutron Spectra
Serpan C., Steele L.
Cryogenic Radiation Effects on NERVA Structural Materials
Begley J., Dixon C., Lombardo J.
Plastic Stability of Zr-2 Fuel Cladding
Weber J.
Influence of Boron on the Creep Rupture Properties of a Neutron Irradiated Precipitation Hardening Iron Base Alloy
Kingsbury F., Lovell A., Moteff J., Smith J.
Role of Pressure Vessel Surveillance Programs in Power Reactors: Summary and Analysis of Asme Panel Discussion
McLaughlin D., Weissert L.
Committee: E10
Paper ID: STP426-EB
DOI: 10.1520/STP426-EB
ISBN-EB: 978-0-8031-6024-8
 ASTM International is a member of CrossRef.
0-8031-6178-6
978-0-8031-6178-8
STP426-EB
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