Effects of Radiation on Structural Metals

    Committee E-10
    Published: 1967

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    Table of Contents

    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

    DOI: 10.1520/STP426-EB

    ISBN-EB: 978-0-8031-6024-8

    ISBN-13: 978-0-8031-6178-8

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