|
|
|
SEDL / STP / STP1447-EB
 |
STP1447
Effects of Radiation on Materials: 21st International Symposium
Grossbeck ML, Allen TR, Lott RG, Kumar AS
Pages: 758
Published: 2004
Other books in this series
|
|
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., Tsai H., Cole J., Ohta J., Dohi K., Kusanagi H.
Study on Ductile Fracture Strain and Fracture Toughness of Irradiated Austenitic Stainless Steels
Nishimura S., Sakamoto H., Kato T.
Investigation of Microstructure and Mechanical Properties of 18Cr-10Ni-Ti Steel Irradiated in the Core of VVER-1000 Reactor
Neustroev V., Dvoretzky V., Ostrovsky Z., Shamardin V., Shimansky G.
Influence of Oversized Solute Additions on Radiation-Induced Microstructure and Microchemistry in Austenitic Stainless Steel
Sencer B., Was G., Fournier L., Kenik E., Simonen E., Bruemmer S.
Solute Addition Effect for Fe-15Cr-20Ni Austenitic Steels Irradiated in Joyo
Fukumoto K., Matsui H., Donomae T., Yamagata I., Akasaka N.
The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels
Kozlov A., Scherbakov E., Averin S., Garner F.
The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel
Busby J., Sowa M., Was G., Was G., Kenik E.
The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel
Hash M., Busby J., Was G., 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
Sokolov M., Nanstad R., Miller M.
On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences
Pechenkin V., Konobeev Y., Stepanov I., Nikolaev Y.
Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ
Nanstad R., Tipping P., Kalkhof R., Sokolov M.
Dependence of Re-embrittlement Rate After Annealing on the Copper, Nickel and Phosphorus Contents in Model Alloys
Valo M., Ehrnstén U., Kohopää J., Debarberis L., Kryukov A., Rintamaa R.
Evaluation of Irradiation Embrittlement of A508 Gr 4N and Comparison to Other Low-Alloy Steels
Wire G., Beggs W., Leax T.
Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects
Burke M., Stofanak R., Hyde J., English C., Server W.
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., Server W., Rosinski S.
A Mechanistically-Guided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment
Rosinski S., Server W., Lott R.
Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region
Hatano S., Sakamoto K., Osaki T.
Master Curve of Irradiated JRQ Material
Serrano M., Perosanz F., Lapeña J.
Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity
Server W., Rosinski S., Lott R.
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
Moskovic R., Crowde M., Flewitt P.
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
Toloczko M., Kumar A., Hamilton M., Jumel S., Van Duysen J., Snead L.
Irradiation Hardening and Microstructural Evolution in Fe-Cu Model Alloys
Kitao T., Kasada R., Kimura A., Nakata H., Fukuya K., Matsui H., Narui M.
Effect of Heat Treatment and Tantalum on Microstructure and Mechanical Properties of Fe-9Cr-2W-0.25V Steel
Klueh R., Hashimoto N., Sokolov M.
Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation
Yamashita S., Oka K., Yoshitake T., Akasaka N., Ukai S., Ohnuki S.
Examination of Postirradiation Deformation Microstructures in F82H
Gelles D., Schäublin R.
Fracture Toughness Characterization of Irradiated F82H in the Transition Region
Sokolov M., Klueh R., Odette G., Shiba K., Tanigawa H.
Incubation Period for Void Swelling and Its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution
Surh M., Sturgeon J., Wolfer W.
Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWR-Relevant Displacement Rates
Porollo S., Konobeev Y., Dvoriashin A., Krigan V., Garner F.
Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr-15Ni-2Mo-1Mn Cladding Irradiated in BN-600
Kozlov A., Portnykh I., Bryushkova S., Kinev E.
Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling
Toloczko M., Garner F.
Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305–335°C
Konobeev Y., Dvoriashin A., Porollo S., Shulepin S., Budylkin N., Mironova E., Garner F.
Kinetics of Helium Bubble Formation in Nuclear and Structural Materials
Schaldach C., Wolfe W.
Bubble Microstructures in Helium Injected Palladium Foils
Gelles D., Causey R., Hertz K., Cowgill D., 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., Tanaka K., Ohnuki S., Takahashi H., Watanabe S., Itoh M.
Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures
Greenwood L., Garner F., Oliver B., Grossbeck M., Wolfe W.
The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys
Cole J., Allen T., Was G., Dropek R., Kenik E.
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
Kimura A., Shibata M., Kasada R., Nakata H., Fujii K., Fukuya K.
The Modeling of Radiation-Induced Phosphorus Segregation at Point Defect Sinks in Dilute Fe-P Alloys
Stepanov I., Pechenkin V., Konobeev Y.
Irradiation Induced Vacancy-Cu Aggregations in Fe-Cu Model Alloys of Reactor Pressure Vessel Steels Studied by Positron Annihilation
Nagai Y., Takadate K., Tang Z., Ohkubo H., Hasegawa M.
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
Toloczko M., Kurtz R., Abe K., Hasegawa A.
Revisiting the Use of SiC as a Post Irradiation Temperature Monitor
Snead L., Williams A., Qualls A.
New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data
Wang J., Rao N.
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
Nogami S., Miwa S., Hasegawa A., Abe K.
Precipitation and Amorphization in Boron Carbide Irradiated by High Energy Helium Ions
Maruyama T., Iwanami M., Ohnuki S., Suda T., Watanabe S., Ikezawa K.
Effects of Pu Decay on a Sodalite Based Ceramic Waste Form
Jue J., Frank S., O'Holleran T., Sinkler W., Barber T., Johnson S., Goff K.
Changes in Mechanical Properties of High-Purity V-4Cr-4Ti-Si, Al, Y Alloys after Neutron Irradiation at Relatively Low Temperatures
Chuto T., Satou M., Hasegawa A., Abe K., Muroga T., 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
Satou M., Nakayashiki H., Chuto T., Chuto T., Hasegawa A., Abe K.
Peculiarities of Structural and Behavioral Changes of Some Zirconium Alloys at Damage Doses of Up to 50 dpa
Kobylyansky G., Novosyolov A., Ostrovsky Z., Shamardin V., Obuhov A., Shishov V., Peregud M., Nikulina A.
Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4
Zu X., Atzmon M., Wang L., You L., Wan F., Was G., Adamson R.
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
 ASTM International is a member of CrossRef.
0-8031-3477-0
978-0-8031-3477-5
STP1447-EB
STP 1447
|
