Effects of Radiation on Materials: 14th International Symposium (Volume II)

    Packan Nicolas, Stoller Roger, Kumar Arvind
    Published: 1990

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    Table of Contents

    Kumar A., Packan N., Stoller R.

    Effects of 50°C Surveillance and Test Reactor Irradiations on Ferritic Pressure Vessel Steel Embrittlement
    Corwin W., Iskander S., Nanstad R., Odette G., Rowcliffe A.

    Application of a United Kingdom Magnox Steel Irradiation Model to the HFIR Pressure Vessel
    Druce S.

    Tensile Properties of Neutron Irradiated A212B Pressure Vessel Steel
    Hamilton M., Heinisch H.

    Experimental Assessments of Gundremmingen RPV Archival Material for Fluence Rate Effects Studies
    Hawthorne J., Hiser A.

    Investigation of Materials from a Decommissioned Reactor Pressure Vessel—A Contribution to the Understanding of Irradiation Embrittlement
    Föhl J., Kussmaul K., Weissenberg T.

    Fine-Scale Microstructural Characterization of Pressure Vessel Steels and Related Materials Using APFIM
    Burke M., Miller M.

    An Analysis of Small Clusters Formed in Thermally Aged and Irradiated FeCu and FeCuNi Model Alloys
    Buswell J., English C., Hetherington M., Phythian W., Smith G., Worrall G.

    SANS and DENS Study of Irradiation Damage in a Reactor Pressure Vessel Material with a Systematic Variation of Irradiation Dose and Heat Treatments
    Bührer W., Frisius F., Solt G., Waeber W.

    Magnetoacoustic and Barkhausen Emission Studies of Neutron Irradiated Iron and Iron-Copper Alloys
    Buttle D., Little E., Scruby C.

    Precipitation in an Aged Fe-0.85 at%Cu Alloy Observed by Muon Spin Rotation Spectroscopy: A Prospective Method of Studying Irradiation Hardening
    Beaven P., Gygax F., Hitti B., Schenck A., Solt G., Tipping P., Waeber W., Zimmermann U.

    An Evaluation of Linde 80 Submerged-Arc Weld Metal Charpy Data Irradiated in the HSST Program
    Lowe A.

    Effects of Radiation on KIc Curves for High Copper Welds
    Haggag F., Iskander S., McCabe D., Menke B., Nanstad R.

    Improved Correlations for Predicting the Effects of Neutron Radiation on Linde 80 Submerged-Arc Weld Metals
    Lowe A., Pegram J.

    Fracture Toughness Shifts and Bounds for Irradiated Reactor Pressure Vessel Materials
    Griesbach T., Server W.

    Comparison of Experimental 41 J Shifts with the Predictions of German KTA 3203 and U.S. NRC Regulatory Guide 1.99
    Ahlf J., Bellmann D.

    The Nil-Ductility Temperature Shift Arising from Irradiation as Predicted Through the French Test Reactor Experiments
    Dussarte D., Miannay D., Soulat P.

    The Effects of Mechanical Stress Gradients on Irradiation-Induced Embrittlement of Pressure Vessel Steel
    Ougouag A., Stubbins J., Williams J.

    The Effect of Nickel on Irradiation Hardening of Pressure Vessel Steels
    Lucas G., Odette G.

    Fracture Resistance of Irradiated Stainless Steel Clad Vessels
    McCabe D.

    Tensile and Charpy Impact Behavior of an Irradiated Three-Wire Series-Arc Stainless Steel Cladding
    Alexander D., Corwin W., Haggag F., Nanstad R.

    Correlation of Cv and Drop-Weight Transition Temperature Increase Caused by Irradiation
    Schmitt F.

    Residual Tensile Properties at Low and High Strain Rates of AISI 316H Predamaged by Creep, Low Cycle Fatigue, and Irradiation to 2 dpa
    Albertini C., Forlani M., Grande A., Iida K., Montagnani M., Pachera A.

    Response of Ferritic/Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K
    Asakura K., Hamada K., Kohyama A., Matsui H.

    Serrated Flow in Irradiated and Partially Denitrided Mild Steel
    Mahmood S., Murty K.

    Effects of High Thermal and High Fast Fluences on the Mechanical Properties of Type 6061 Aluminum on the HFBR
    Czajkowski C., Tichler P., Weeks J.

    Charpy Impact Test Results of Ferritic Alloys Irradiated to 10 dpa at 55°C
    Gelles D., Hu W.

    Fracture Behavior of Ferritic Steels Irradiated at 50°C in the High-Flux Isotope Reactor (HFIR)
    Huang F.

    Evaluation of the Fracture Toughness of Irradiated Stainless Steel Using Short Rod Specimens
    Clarke W., Ranganath S., White M.

    Effect of Specimen Size on the Upper Shelf Energy of Ferritic Steels
    Garner F., Hamilton M., Kumar A.

    Evaluation of Irradiation Embrittlement by Instrumented Impact Testing
    Anantharaman S., Chatterjee S., Sivaramakrishnan K., Viswanathan U.

    Evaluation of Ring Tensile Test Results—A Semiempirical Approach
    Anantharaman S., Balakrishnan K., Chatterjee S., Sivaramakrishnan K.

    Irradiation Creep Behavior of the Fusion Heats of HT9 and Modified 9Cr-1 Mo Steels
    Garner F., Puigh R.

    Irradiation Creep in Austenitic Stainless Steels at 60 to 400°C with a Fusion Reactor Helium to dpa Ratio
    Grossbeck M., Mansur L., Tanaka M.

    Influence of Thermomechanical Treatment and Environmental History on Creep, Swelling, and Embrittlement of AISI 316 at 400°Cand 130 dpa
    Garner F., Porter D., Wood E.

    Swelling and In-Pile Creep Behavior of Some 15Cr15NiTi Stainless Steels in the Temperature Range 400 to 600°C
    Bergmann H., Herschbach K., Schneider W.

    The Cantilever Beam Method for Simulating Irradiation Creep and Growth
    Hoelke C., Parsons J.

    Effects of Neutron Irradiation to 98 dpa on the Swelling of Various Copper Alloys
    Brager H., Garner F.

    EURAC: A Concept for a European Accelerator Neutron Source
    Bishop G., Kley W., Perlado J., Sinha A.

    Analysis of Transmutation Nuclide Production in a Spallation Neutron Source
    Sinha A., Srinivasan M.

    Radiation Damage Calculations for Compound Materials
    Greenwood L.

    Neutron Spectra Calculations for Ex-Core Irradiation Experiments at the Buffalo Reactor
    Hawthorne J., McGarry E., Prillinger G.

    Consideration of Calculated and Experimental Neutron Dosimetry for Out-of-Core Metallurgy Irradiation Experiments at the Buffalo Reactor
    Hawthorne J., McGarry E., Prillinger G., Rogers J.

    Neutron-Induced Swelling of Commercial Alloys at Very High Exposures
    Garner F., Gelles D.

    Effect of Neutron Radiation on Mechanical Properties of Permanent Near Core Structures
    Tavassoli A.

    Influence of Swelling on Irradiated CW Titanium Modified 316 Embrittlement
    Cauvin R., Fissolo A., Hugot J., Levy V.

    The Influence of Creep Damage and Neutron Irradiation on the Tensile Properties of Type 304 Stainless Steel
    Schaaf B.

    Simulated Transient Behavior of HT9 Cladding
    Cannon N., Hamilton M., Huang F.

    The Swelling Behavior of Titanium-Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phénix
    Blanchard P., Boulbin E., Dubuisson P., Hugot J., Maillard A., Pelletier M., Seran J., Touron H.

    Irradiation Creep and Swelling of OX16H15M3B Steel and Its Modification 0X16H15M3BP Steel
    Bibilashvili Y., Golovanov V., Golovnin I., Kalashnik G., Neustroev V., Povstyanko A., Romaneev V., Shamardin V.

    Operational Behavior of FBR Mixed Oxide Fuel Pins
    Biermann W., Ehrlich K., Mühling G.

    In Situ High Voltage Electron Microscopy Investigation of Catastrophic Swelling in Uranium Intermetallic Fuels
    Allen C., Birtcher R., Hofman G., Rehn L.

    The Effect of Crystal Structure Stability on Swelling in Intermetallic Uranium Compounds
    Birtcher R., Hofman G., Rest J.

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1046V2-EB

    ISBN-EB: 978-0-8031-8887-7

    ISBN-13: 978-0-8031-1266-7

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