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Digital Library / STP / STP1447-EB
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Effects of Radiation on Materials: 21st International Symposium
Grossbeck ML
Pages: 758
Published: 2004
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Table of Contents
Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate
Allen TR, Tsai H, Cole JI, 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 VS, Dvoretzky VG, Ostrovsky ZE, Shamardin VK, Shimansky GA
Influence of Oversized Solute Additions on Radiation-Induced Microstructure and Microchemistry in Austenitic Stainless Steel
Sencer BH, Was GS, Fournier L, Kenik EA, Simonen EP, Bruemmer SM
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 AV, Scherbakov EN, Averin SA, Garner FA
The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel
Busby JT, Sowa MM, Was GS, Kenik EA
The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel
Hash MC, Busby JT, Was GS
Martensitic Transformations in Neutron Irradiated and Helium Implanted Stainless Steels
Kadyrzhanov KK, Maksimkin OP
Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld
Sokolov MA, Nanstad RK, Miller MK
On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences
Pechenkin VA, Konobeev YV, Stepanov IA, Nikolaev YA
Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ
Nanstad RK, Tipping P, Kalkhof RD, Sokolov MA
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 GL, Beggs WJ, Leax TR
Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects
Burke MG, Stofanak RJ, Hyde JM, English CA, Server WL
Effect of Stress Relief Time on the Transition Temperature of Linde 80 Welds
Hall JB, Yoon KK
Critical Review of Through-Wall Attenuation of Mechanical Properties in RPV Steels
English CA, Server WL, Rosinski ST
A Mechanistically-Guided Charpy Embrittlement Correlation for Reactor Pressure Vessel Integrity Assessment
Rosinski ST, Server WL, Lott RG
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 FJ, Lapeña J
Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity
Server WL, Rosinski ST, Lott RG
The Technical Foundations of a Unified Adjusted Reference Temperature for RPV Fracture Toughness
Lott RG, Rosinski ST, Server WL
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 MJ, Flewitt PEJ
The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels
Stoller RE
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 MB, Kumar AS, Hamilton ML, Jumel S, Van Duysen JC, Snead LL
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 RL, Hashimoto N, Sokolov MA
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 DS, Schäublin R
Fracture Toughness Characterization of Irradiated F82H in the Transition Region
Sokolov MA, Klueh RL, Odette GR, Shiba K, Tanigawa H
Incubation Period for Void Swelling and Its Dependence on Temperature, Dose Rate, and Dislocation Structure Evolution
Surh MP, Sturgeon JB, Wolfer WG
Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWR-Relevant Displacement Rates
Porollo SI, Konobeev YV, Dvoriashin AM, Krigan VM, Garner FA
Dependence of Maximum Swelling Temperature on Damage Dose in Cold Worked 16Cr-15Ni-2Mo-1Mn Cladding Irradiated in BN-600
Kozlov AV, Portnykh IA, Bryushkova SV, Kinev EA
Stress and Temperature Dependence of Irradiation Creep of Selected FCC and BCC Steels at Low Swelling
Toloczko MB, Garner FA
Irradiation Creep and Swelling of Russian Ferritic-Martensitic Steels Irradiated to Very High Exposures in the BN-350 Fast Reactor at 305335°C
Konobeev YV, Dvoriashin AM, Porollo SI, Shulepin SV, Budylkin NI, Mironova EG, Garner FA
Kinetics of Helium Bubble Formation in Nuclear and Structural Materials
Schaldach CM, Wolfe WG
Bubble Microstructures in Helium Injected Palladium Foils
Gelles DS, Causey RA, Hertz K, Cowgill DF, Schäublin R
Fatigue Response and Life Prediction of Selected Reactor Materials
Li M, Stubbins JF
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 LR, Garner FA, Oliver BM, Grossbeck ML, Wolfe WG
The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys
Cole JI, Allen TR, Was GS, Dropek RB, Kenik EA
Inter-Granular Phosphorus Segregation in Ferritic Steels
Faulkner RG, Flewitt PEJ, 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 IA, Pechenkin VA, Konobeev YV
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 VA
Tensile Property Estimates Obtained Using a Low Compliance Shear Punch Test Fixture
Toloczko MB, Kurtz RJ, Abe K, Hasegawa A
Revisiting the Use of SiC as a Post Irradiation Temperature Monitor
Snead LL, Williams AM, Qualls AL
New Methodologies for Developing Radiation Embrittlement Models and Trend Curves of the Charpy Impact Test Data
Wang JA, Rao NSV
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-F, Frank SM, O'Holleran TP, Sinkler W, Barber TL, Johnson SG, Goff KM
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 ML
Varying Temperature Irradiation Effects of V-4Cr-4Ti Alloy with Small Addition of Si, Al and Y
Satou M, Nakayashiki H, 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 GP, Novosyolov AE, Ostrovsky ZE, Shamardin VK, Obuhov AV, Shishov VN, Peregud MM, Nikulina AV
Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4
Zu XT, Atzmon M, Wang LM, You LP, Wan FR, Was GS, Adamson RB
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
 ASTM International is a member of CrossRef.
0-8031-3477-0
978-0-8031-3477-5
STP1447-EB
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