STP1447

    Effects of Radiation on Materials: 21st International Symposium

    Grossbeck ML, Allen TR, Lott RG, Kumar AS

    Pages: 758

    Published: 2004

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    Fifty-nine peer-reviewed papers provide the latest international research on nuclear materials.

    Although the primary focus is on pressure vessel steels, including mechanical properties and microstructures, it contains papers on the latest research on fundamentals of radiation effects in materials as well as on stainless steels and nonferrous alloys. It has a truly international flavor containing twenty-six papers from outside the United States.

    Sections cover:

    • Austenitic Stainless Steels

    • Pressure Vessel Steels—Properties and Mechanisms

    • Pressure Vessel Steels—Analysis and Prediction

    • Ferritic Steels—Model and Low Activation Alloys

    • Swelling and Irradiation Creep

    • Radiation Effects

    • Radiation-Induced Segregation and Transmutation

    • Measurement Techniques and Modeling Studies

    • Radiation-Induced Segregation and Transmutation

    • Measurement Techniques and Modeling Studies

    • Ceramic Materials

    • Vanadium Alloys

    • Zirconium and Copper Alloys


    Table of Contents

    Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate
    Allen T., Cole J., Dohi K., Kusanagi H., Ohta J., Tsai H.

    Study on Ductile Fracture Strain and Fracture Toughness of Irradiated Austenitic Stainless Steels
    Kato T., Nishimura S., Sakamoto H.

    Investigation of Microstructure and Mechanical Properties of 18Cr-10Ni-Ti Steel Irradiated in the Core of VVER-1000 Reactor
    Dvoretzky V., Neustroev V., Ostrovsky Z., Shamardin V., Shimansky G.

    Influence of Oversized Solute Additions on Radiation-Induced Microstructure and Microchemistry in Austenitic Stainless Steel
    Bruemmer S., Fournier L., Kenik E., Sencer B., Simonen E., Was G.

    Solute Addition Effect for Fe-15Cr-20Ni Austenitic Steels Irradiated in Joyo
    Akasaka N., Donomae T., Fukumoto K., Matsui H., Yamagata I.

    The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels
    Averin S., Garner F., Kozlov A., Scherbakov E.

    The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel
    Busby J., Kenik E., Sowa M., Was G.

    The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel
    Busby J., Hash M., Was G.

    Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels
    Kadyrzhanov K., Maksimkin O.

    Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld
    Miller M., Nanstad R., Sokolov M.

    On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences
    Konobeev Y., Nikolaev Y., Pechenkin V., Stepanov I.

    Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ
    Kalkhof R., Nanstad R., Sokolov M., Tipping P.

    Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys
    Debarberis L., Ehrnstén U., Kohopää J., Kryukov A., Rintamaa R., Valo M.

    Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other Low-Alloy Steels
    Beggs W., Leax T., Wire G.

    Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects
    Burke M., English C., Hyde J., Server W., Stofanak R.

    Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds
    Hall J., Yoon K.

    Critical Review of Through-Wall Attenuation of Mechanical Properties in RPV Steels
    English C., Rosinski S., Server W.

    A Mechanistically-Guided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment
    Lott R., Rosinski S., Server W.

    Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region
    Hatano S., Osaki T., Sakamoto K.

    Master Curve of Irradiated JRQ Material
    Lapeña J., Perosanz F., Serrano M.

    Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity
    Lott R., Rosinski S., Server W.

    The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness
    Lott R., Rosinski S., Server W.

    A Statistical Analysis of the Effect of Neutron Irradiation Dose and Dose Spectrum on Changes of Charpy Impact Energy for C-Mn Steels
    Crowde M., Flewitt P., Moskovic R.

    The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels
    Stoller R.

    Hardening Mechanisms in Ferritic/Martensitic Steels
    Baluc N., Schäublin R., Spätig P., Victoria M.

    Effects of Copper Content on the Tensile Properties of Iron-Copper Alloys
    Hamilton M., Jumel S., Kumar A., Snead L., Toloczko M., Van Duysen J.

    Irradiation Hardening and Microstructural Evolution in Fe-Cu Model Alloys
    Fukuya K., Kasada R., Kimura A., Kitao T., Matsui H., Nakata H., Narui M.

    Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe-9Cr-2W-0.25V Steel
    Hashimoto N., Klueh R., Sokolov M.

    Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation
    Akasaka N., Ohnuki S., Oka K., Ukai S., Yamashita S., Yoshitake T.

    Examination of Postirradiation Deformation Microstructures in F82H
    Gelles D., Schäublin R.

    Fracture Toughness Characterization of Irradiated F82H in the Transition Region
    Klueh R., Odette G., Shiba K., Sokolov M., Tanigawa H.

    Incubation Period for Void Swelling and Its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution
    Sturgeon J., Surh M., Wolfer W.

    Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWR-Relevant Displacement Rates
    Dvoriashin A., Garner F., Konobeev Y., Krigan V., Porollo S.

    Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr-15Ni-2Mo-1Mn Cladding Irradiated in BN-600
    Bryushkova S., Kinev E., Kozlov A., Portnykh I.

    Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling
    Garner F., Toloczko M.

    Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C
    Budylkin N., Dvoriashin A., Garner F., Konobeev Y., Mironova E., Porollo S., Shulepin S.

    Kinetics of Helium Bubble Formation in Nuclear and Structural Materials
    Schaldach C., Wolfe W.

    Bubble Microstructures in Helium Injected Palladium Foils
    Causey R., Cowgill D., Gelles D., Hertz K., Schäublin R.

    Fatigue Response and Life Prediction of Selected Reactor Materials
    Li M., Stubbins J.

    Detection of Radiation-Enhanced Diffusion by Means of Neutron-Irradiated Diffusion Couples of Fe-Cr-Ni System
    Akasaka N., Itoh M., Ohnuki S., Takahashi H., Tanaka K., Watanabe S.

    Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures
    Garner F., Greenwood L., Grossbeck M., Oliver B., Wolfe W.

    The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys
    Allen T., Cole J., Dropek R., Kenik E., Was G.

    Inter-Granular Phosphorus Segregation in Ferritic Steels
    Faulkner R., Flewitt P., Lu Z.

    Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels
    Fujii K., Fukuya K., Kasada R., Kimura A., Nakata H., Shibata M.

    The Modeling of Radiation-Induced Phosphorus Segregation at Point Defect Sinks in Dilute Fe-P Alloys
    Konobeev Y., Pechenkin V., Stepanov I.

    Irradiation Induced Vacancy-Cu Aggregations in Fe-Cu Model Alloys of Reactor Pressure Vessel Steels Studied by Positron Annihilation
    Hasegawa M., Nagai Y., Ohkubo H., Takadate K., Tang Z.

    Heavy Ion Fluence Measurements Based on Radiation Effects Generated in CTA Foils
    Peimel-Stuglik Z., Skuratov V.

    Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture
    Abe K., Hasegawa A., Kurtz R., Toloczko M.

    Revisiting the Use of SiC as a Post Irradiation Temperature Monitor
    Qualls A., Snead L., Williams A.

    New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data
    Rao N., Wang J.

    Mechanical and Structural Property Changes of Monolithic SiC and Advanced SiC/SiC Composites due to Low Temperature He+-Ion Irradiation and Post-Irradiation High Temperature Annealing
    Abe K., Hasegawa A., Miwa S., Nogami S.

    Precipitation and Amorphization in Boron Carbide Irradiated by High Energy Helium Ions
    Ikezawa K., Iwanami M., Maruyama T., Ohnuki S., Suda T., Watanabe S.

    Effects of Pu Decay on a Sodalite Based Ceramic Waste Form
    Barber T., Frank S., Goff K., Johnson S., Jue J., O'Holleran T., Sinkler W.

    Changes in Mechanical Properties of High-Purity V-4Cr-4Ti-Si, Al, Y Alloys after Neutron Irradiation at Relatively Low Temperatures
    Abe K., Chuto T., Hasegawa A., Muroga T., Satou M., Yamamoto N.

    Creep Deformation in V-4Cr-4Ti in a Low-Oxygen Lithium Environment
    Grossbeck M.

    Varying Temperature Irradiation Effects of V-4Cr-4Ti Alloy with Small Addition of Si, Al and Y
    Abe K., Chuto T., Hasegawa A., Nakayashiki H., Satou M.

    Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 dpa
    Kobylyansky G., Nikulina A., Novosyolov A., Obuhov A., Ostrovsky Z., Peregud M., Shamardin V., Shishov V.

    Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4
    Adamson R., Atzmon M., Wan F., Wang L., Was G., You L., Zu X.

    Microstructure Response in Copper and Copper Alloys Irradiated with Fission Neutrons with Controlled Temperature Variations
    Muroga T., Watanabe H.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1447-EB

    DOI: 10.1520/STP1447-EB

    ISBN-EB: 978-0-8031-5494-0

    ISBN-PRINT: 978-0-8031-3477-5

    ASTM International is a member of CrossRef.

    0-8031-3477-0
    978-0-8031-3477-5
    STP1447-EB