STP1325

    Effects of Radiation on Materials: 18th International Symposium

    Nanstad RK, Hamilton ML, Garner FA, Kumar AE
    Published: 1999


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    Features the most current research from an international body of leading experts on how radiation impacts the microstructure and mechanical properties of a wide range of metals.

    This comprehensive publication includes 71 peer-reviewed papers organized into the following key areas:

    • radiation damage mechanisms and modeling in reactor pressure vessel steels

    • relevant mechanical properties and test techniques for pressure vessel steels

    • grain boundary segregation studies

    • microstructural aspects of annealing; recovery of properties by thermal annealing

    • embrittlement correlations

    • damage characterization using nondestructive techniques

    • segregation and properties of austenitic alloys

    • irradiation creep and swelling in structural and austenitic alloys

    • microstructural studies and mechanical properties experiments on ferritic and ferritic-martensitic alloys

    • and experiments using copper and copper alloys, vanadium alloys and other materials including aluminum, beryllium, zirconium and sapphire.


    Table of Contents

    Irradiation Creep in Nickel Containing and in Manganese Containing Stainless Steel Alloys
    Hausen H., Schüle W.

    Irradiation Hardening of Pressure Vessel Steels at 60°C: The Role of Thermal Neutrons and Boron
    Klingensmith D., Lucas G., Odette G.

    The Impact of Mobile Point Defect Clusters in a Kinetic Model of Pressure Vessel Embrittlement
    Stoller R.

    An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper, Phosphorus and Nickel Additions
    Buswell J., Little E., Sinclair R.

    An Assessment of Potential Gamma Ray Enhancement of Embrittlement in ABWR Pressure Vessel Walls
    Garner F., Greenwood L., Roy P.

    Dynamic Finite Element Modeling of the Upper Shelf Energy of Precracked Charpy Specimens of Neutron Irradiated Weld Metal 72W
    Hamilton M., Kumar A., Sidener S.

    Anomalous Hardening in Model Alloys and Steels Thermally Aged at 290°C and 350°C: Implications to Low Flux Irradiation Embrittlement
    Klingensmith D., Lucas G., Odette G.

    Small Angle Neutron Scattering Study of Linde 80 RPV Welds
    Lucas G., Odette G., Pavinich W., Spooner S., Wirth B.

    Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70
    McCabe D., Nanstad R., Swain R.

    Fracture Toughness Testing of Linde 1092 Reactor Vessel Welds in the Transition Range Using Charpy-Sized Specimens
    Hoffman C., Hour K., Pavinich W., Yoon K.

    Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels
    Nanstad R., Sokolov M.

    Miniaturized Charpy Test for Reactor Pressure Vessel Embrittlement Characterization
    Manahan M.

    Use of Forces from Instrumented Charpy V-Notch Testing to Determine Crack-Arrest Toughness
    Hutton J., Iskander S., McCabe D., Nanstad R., Sokolov M., Thomas D.

    The Ductile-Brittle Transition Behaviour of Submerged-Arc Weldments Following High Temperature Exposure
    Beere W., Bolton C., Fenton S., Fidler R., Jones R.

    Irradiation of Vessel Materials Using KORPUS Facility of RBT-6 Reactor
    Golovanov V., Markina N., Raetsky V., Seriodkin S., Tsykanov V.

    Auger Spectroscopy of Magnox Pressure Vessel Steels
    Fisher S., Knowles G., Lee B.

    Phosphorus Free Energy Change Associated with Segregation to Grain Boundaries in Submerged-Arc Welds
    Mendes C.

    Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening
    Gurovich B., Korolev Y., Kuleshova E., Nikolaev Y., Shtrombakh Y.

    Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels
    English C., Foreman A., Gage G., Hyde J., McElroy R., Ray P., Vatter I.

    The Effect of Heat Treatment on Phosphorus Segregation in a Submerged-Arc Weld Metal
    Beere W., Buswell J.

    SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions
    Lucas G., Odette G., Sokolov M., Spooner S., Wirth B.

    Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals after Irradiation and Annealing
    Böhmert J., Brauer G., Große M., Nitzsche P.

    Hardness and Microstructural Response to Thermal Annealing of Irradiated ASTM A533B Class 1 Plate Steel
    Gelles D., Hamilton M., Kumar A., Reinhart D., Rosinski S.

    Effects of Damage Rate on Irradiation Hardening and Post-irradiation Annealing Characteristics of Carbon Steel
    Idei Y., Kizaki M., Onizawa K., Suzuki M.

    Experimental Tests of Irradiation-Anneal-Reirradiation Effects on Mechanical Properties of RPV Plate and Weld Materials
    Hawthorne J., Rochau G., Rosinski S.

    Comparison of Different Experimental and Analytical Measures of the Thermal Annealing Response of Neutron-Irradiated RPV Steels
    Iskander S., Nanstad R., Sokolov M.

    The Annealing Recovery of The Palisades Nuclear Power Plant Surveillance Material Using Weld Reconstitution
    Friedman E., Kneeland J., Lott R., Server W., Terek E., Williams J.

    Design of an Annealing Supplemental Surveillance Program for the Palisades Reactor Pressure Vessel
    Hanson J., Kneeland J., Lott R., Server W.

    Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel
    Biemiller E., Carter R., Chaouadi R., Fabry A., Puzzolante J., Rosinski S., Van de Velde J.

    Role and Experience with Thermal Monitors in Reactor Vessel Surveillance Capsules
    Lowe A.

    A Consideration of Scatter in Radiation Damage Trend Curves for Reactor Pressure Vessel Steel Plate Materials
    Griesbach T., Server W.

    Refinements to Pressure Vessel Steel Embrittlement Correlations
    Byrne S., Hardies R.

    Development of Embrittlement Prediction Models for U.S. Power Reactors and The Impact of The Heat-Affected Zone to Thermal Annealing
    Wang J.

    Empirical Correlation of Observed Three Stages of Fast Neutron Irradiation Hardening and Embrittlement in WWER-440 Pressure Vessel Materials
    Korolev Y., Lessa R., Levit V., Tipping P.

    Evaluation of Irradiated Pressure Vessel Steel by Mechanical Tests and Positron Annihilation Lineshape Analysis
    Maeda N., Nakamura N., Ohta Y., Yoshida K.

    Detection of Radiation Damage in Low Alloy Steel Using a Squid Sensor
    Maeda N., Morinaka R., Otaka M., Shimizu S., Yamaguchi A.

    Nondestructive Evaluation of Neutron Irradiation Embrittlement for Reactor Vessel Steel by Magnetomechanical Acoustic Emission Technique
    Chujou N., Hirasawa T., Komura I., Maeda N., Saito K., Yamaguchi A.

    Changes in Electromagnetic Properties of a Low-Alloy Steel Caused by Neutron Irradiation
    Goto T., Kamimura T., Kumano S., Maeda N., Takeuchi I., Yamaguchi A.

    Detection of Irradiation Embrittlement of Low-Alloy Steel for Nuclear Reactor Pressure Vessels Using a Probe Type Eddy Current Sensor
    Kohno K., Maeda N., Sugibayashi T., Yamaguchi A.

    The Effect of Ordering on Radiation-Induced Segregation in Austenitic Iron- and Nickel-Base Alloys
    Allen T., Was G.

    The Modelling of Combined Radiation-Induced and Thermal Non-Equilibrium Segregation of Chromium in Neutron-Irradiated Austenitic Stainless Steels
    Faulkner R., Fisher S., Goodwin C.

    Radiation-Induced Instability of MnS Precipitates and its Possible Consequences on Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels
    Chung H., Garner F., Sanecki J.

    Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Held Joints after Neutron Irradiation
    Hamada S., Hishinuma A., Ioka I., Jitsukawa S., Robertson J., Shiba K.

    Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel after Low Temperature Neutron Irradiation
    Grossbeck M., Ioka I., Jitsukawa S., Robertson J., Rowcliffe A.

    Microstructures in Neutron Irradiated Fe-Cr-Ni-P-Ti Model Austenitic Alloys Doped with 10B
    Kurishita H., Muroga T., Watanabe H., Yoshida N.

    Behavior of Fe-Cr-Ni-xP-yTi Alloys under Electron/He Ion Dual Beam Irradiation
    Hidaka Y., Kinoshita H., Takahashi H., Tsuchida H., Watanabe S.

    Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR
    Adaway S., Garner F., Munro B., Standring J., Toloczko M.

    Irradiation Creep at Temperatures of 400°C and Below for Application to Near-Term Fusion Devices
    Gibson L., Grossbeck M., Jitsukawa S., Mansur L., Turner L.

    Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400–600°C
    Garner F., Toloczko M.

    Evaluation of Low-Temperature Swelling in Austenitic Stainless Steels
    Katoh Y.

    A Reevaluation of Helium/dpa and Hydrogen/dpa Ratios for Fast Reactor and Thermal Reactor Data Used in Fission-Fusion Correlations
    Garner F., Greenwood L., Oliver B.

    The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation
    Akasaka N., Hattori K., Onose S., Ukai S.

    The Dependence of Swelling on Phosphorus Content in Stainless Steels Containing High Silicon Levels
    Garner F., Reinhart D.

    Neutron Irradiation Creep at 100°C on 316L, AMCR, and Welded 316L Stainless Steel Alloys
    Hausen H., Schüle W.

    Effect of Radiation-Induced Segregation on Precipitate Stability and Swelling in Irradiated Alloys
    Epov G., Konobeev Y., Pechenkin V., Stepanov I.

    Microstructural and Microchemical Characterisation of Ferritic Ex-Service Magnox Control Rod Sheath Material
    Fisher S., Spellward P., Walmsley J.

    Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix
    Dubuisson P., Grislin I., Hugon M., Séran J., Schill R.

    The Consequences of Helium Production and Nickel Additions on Microstructural Development in Isotopically Tailored Ferritic Alloys
    Gelles D.

    Tensile and Charpy Impact Properties of Irradiated Reduced Activation Ferritic Steels
    Alexander D., Klueh R.

    Impact Behavior of Low Activation Steels at 30 dpa
    Gelles D., Hamilton M., Schubert L.

    Electron Microscopy of Precipitation and Age Hardening in Fe-0.6Cu Model Alloy
    Kawanishi H., Suzuki M.

    Brazed Dispersion Strengthened Copper: The Effect of Neutron Irradiation and Transmutation on Bond Integrity
    Edwards D., Garner F., Hamilton M., Samal P., Troxell J.

    Void Swelling of Copper and Copper Alloys Induced by Heavy Ion Irradiation
    Matue T., Muroga T., Watanabe H., Yoshida N.

    Radiation-Enhanced Diffusion of 63Ni in Nickel and in Copper
    Schüle W.

    The Effects of Irradiation on the Mechanical Properties of 6061-T651 Aluminum Base Metal and Weldments
    Alexander D.

    Irradiation Induced Growth and Microstructure Evolution of Zr-1.2Sn-1Nb-0.4Fe Under Neutron Irradiation to High Doses
    Kobylyansky G., Nikulina A., Peregud M., Shamardin V., Shishov V., Tselischev A.

    The Neutron Irradiation Effect on the Mechanical Properties and Structure of Beryllium
    Bagautdinov R., Fabritsiev S., Pokrovsky A.

    In-Situ Radio-Luminescence from Sapphires Under Fission Reactor Irradiation
    Jensen B., Kakuta T., Kayano H., Nakazawa S., Narui M., Sagawa T., Shikama T.

    The Effects of Constraint, Loading Rate and Irradiation on the Toughness-Temperature Behavior of a V-4Cr-4Ti Alloy
    Donahue E., Lucas G., Odette G., Sheckherd J.

    Effects of Helium on Void Swelling Behavior of Vanadium Alloys Using Dual Ion Beam Irradiation
    Garner F., Iwai T., Sekimura N.

    Effects of Low Temperature Irradiation on the Mechanical Properties of V-4Cr-4Ti
    Alexander D., Bloom E., Eatherly W., Gubbi A., Rowcliffe A., Snead L., Zinkle S.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1325-EB

    DOI: 10.1520/STP1325-EB

    ISBN-EB: 978-0-8031-5395-0

    ISBN-13: 978-0-8031-2614-5

    ASTM International is a member of CrossRef.

    0-8031-2614-X
    978-0-8031-2614-5
    STP1325-EB