STP570

    Properties of Reactor Structural Alloys After Neutron or Particle Irradiation

    Baroch CJ
    Published: 1975


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    The seventh ASTM International Symposium on Effects of Radiation on Structural Materials was held in Gatlinburg, Tenn., 11-13 June 1974. Committee E10 on Nuclear Applications and Measurement of Radiation Effects sponsored the symposium. C. J. Baroch, Babcock and Wilcox Company, presided as symposium chairman, and F. R. Shober, Westinghouse Hanford Company, served as symposium co-chairman.


    Table of Contents

    Introduction
    Baroch C.

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    General Discussion

    Influence of Defects in Body-Centered Cubic Iron on Simulated Low-Energy Displacement Cascades
    Brumovský M.

    Decrease of Ductility Upon Neutron Irradiation in Iron Alloys and Columbium
    Igata N., Kayano H., Watanabe K.

    Interaction of Strain and Radiation Damages in a Pressure Vessel Steel
    Brumovský M.

    Strength and Notch Ductility of Selected Structural Alloys After High Fluence 550°F (288°C) Irradiation
    Hawthorne J., Watson H.

    Reactor Vessel Material Surveillance Program
    Cuttica G., Galliani M., Mager T., Yanichko S.

    Evaluation of Commercial Production A533-B Plates and Weld Deposits Tailored for Improved Radiation Embrittlement Resistance
    Groeschel R., Hawthorne J., Koziol J.

    Effect of Impurity Concentration on the Change in Fracture Toughness of AISI Type 403 Stainless Steel with Fast Neutron Radiation
    Hosbons R., Pacey A., Wotton B.

    Radiation Damage and Fatigue Evaluation of Reactor End Fittings
    Mukherjee B.

    Effect of Irradiation at 130, 650, and 775°F on Tensile Properties of Zircaloy-4 at 70, 650, and 775°F
    Baroch C.

    Effect of Neutron Irradiation on Types 316 and 321 and Sandvik 12R72 Stainless Steels
    Garr K., Kramer D., Pard A.

    Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures
    Michel D., Smith H.

    Fatigue and Creep-Fatigue Behavior of Irradiated and Unirradiated Type 308 Stainless Steel Weld Metal at Elevated Temperatures
    Harper M., Korth G.

    Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds
    Shahinian P.

    Dose Dependence of Irradiation Creep of Zircaloy-2
    Wood D.

    Improvement of Creep Properties in a Helium Injected Austenitic Stainless Steel
    Furuta T., Kawasaki S., Nagasaki R., Uematsu K.

    Creep and Swelling Deformation in Structural Materials During Fast-Neutron Irradiation
    Ashkin M., Boltax A., Wolfer W.

    Multiaxial Primary Irradiation Creep Equations for Reactor Structural Materials
    Gittus J.

    Surface Reaction Limited Void Growth
    Li C., Mansur L., Okamoto P., Taylor A.

    Spectral Effects in Neutron and Charged Particle Irradiations
    Doran D., McElroy W., Simons R.

    Postirradiation Properties of the 6061-T6 Aluminum High Flux Isotope Reactor Hydraulic Tube
    Farrell K., Richt A.

    Comparison of Displacement and Gas Production Rates in Current Fission and Future Fusion Reactors
    Abdou M., Doran D., Kulcinski G.

    Helium Mobility and Bubble Formation in Type 316 Stainless Steel, Aluminum, and Vanadium
    Pieper A., Smidt F.

    Irradiation-Induced Swelling Variations Resulting from Compositional Modifications of Type 316 Stainless Steel
    Bates J.

    Effect of the Degree of Cold Work on the Irradiation-Induced Swelling of Type 316 Stainless Steel
    Challenger K., Lauritzen T.

    Dimensional Stability of Neutron Irradiated Molybdenum
    Jang H., Moteff J.

    Dimensional Stability of Tantalum During Fast Neutron Irradiation
    Bell I., Bland J., Murgatroyd R.

    Influence of High Voltage Electron Microscope Irradiation on Neutron-Produced Microstructures in Stainless Steels
    Garner F., Laidler J., Mastel B., Thomas L.

    Swelling in Electron-Irradiated Type 316 Stainless Steel
    Garner F., Laidler J., Mastel B.

    Void Formation in Cold-Worked Type 316 Stainless Steel Irradiated with 1-MeV Protons
    Keefer D., Pard A.

    Void Formation in an Ion Bombarded Cold-Worked Stainless Steel
    Brimhall J., Nishikawa T., Uematsu K.

    Effect of Irradiation Parameters on Nickel-Ion Damage in Nickel
    Malmberg P., Smidt F., Sprague J., Westmoreland J.

    Void Swelling in the Iron-Chromium-Nickel System—A Survey by Nickel Ion Bombardment
    Johnston W., Lauritzen T., Rosolowski J., Turkalo A.

    Swelling Resistance Induced by Grain Refinement and Particle Dispersion in Austenitic Stainless Steel During High Energy Electron Irradiation
    Singh B.

    Development Programs on Irradiation Embrittlement of Low Alloy Pressure Vessel Steels in the Federal Republic of Germany
    Pachur D., Sievers G.

    Swelling and Irradiation Induced Microstructural Changes in Nickel-Based Alloys
    Bleiberg M., Choyke J., Diamond S., Rowcliffe A., Spitznagel J.

    Irradiated Steels Behavior in Long-Term Load Tests
    Finko A., Prochorov V., Shamardin V., Votinov S.

    Motion of Dislocation in Stainless Steel During the Fast Neutron Irradiation
    Altovskii I., Astrakhantsev S., Elesin L., Gurovich B., Platonov P., Ryazanov A.


    Committee: E10

    Paper ID: STP570-EB

    DOI: 10.1520/STP570-EB

    ISBN-EB: 978-0-8031-4653-2

    ISBN-13: 978-0-8031-0539-3

    ASTM International is a member of CrossRef.

    0-8031-0539-8
    978-0-8031-0539-3
    STP570-EB