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Digital Library / STP / STP1270-EB
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Effects of Radiation on Materials: 17th International Symposium
Gelles DS
Pages: 1161
Published: 1996
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Table of Contents
Mechanisms Controlling the Composition Influence on Radiation Hardening and Embrittlement of Iron-Base Alloys
Nikolaev VA, Rybin VV
Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering
Stoller RE
The B&W Owners Group Program for Microstructural Characterization and Radiation Embrittlement Modelling of Linde 80 Reactor Vessel Welds
Pavinich WA, Harbison LS
Irradiation Embrittlement Modelling of Linde 80 Weld Metals
McElroy RJ, Lowe AL
Modeling of Irradiation Embrittlement and Annealing/Recovery in Pressure Vessel Steels
Lott RG, Freyer PD
The Modelling of Irradiation Embrittlement in Submerged-Arc Welds
Bolton CJ, Buswell JT, Jones RB, Moskovic R, Priest RH
The Modelling of Irradiation-Enhanced Phosphorus Segregation in Neutron Irradiated Reactor Pressure Vessel Submerged-Arc Welds
Druce SG, English CA, Foreman AJE, McElroy RJ, Vatter IA, Bolton CJ, Buswell JT, Jones RB
Research to Understand the Embrittlement Behavior of Yankee/BR3 Surveillance Plate and Other Outlier RPV Steels
Fabry A, Van de Velde J, Puzzolante JL, Van Ransbeeck T, Verstrepen A, Biemller EC, Carter RG, Petrova T
Electron Microscopy and Small Angle Neutron Scattering Study of Precipitation in Low Alloy Steel Submerged-Arc Welds
Williams TJ, Phythian WJ
Radiation Damage Studies Using Small-Angle Neutron Scattering
Albertini G, Carsughi F, Coppola R, Rustichelli F, Stefanon M
Damage Structures of Proton Irradiated Fe-0.3wt.%Cu Alloy
Kimura A, Shibamoto H, Yuya H, Hasegawa M, Yamaguchi S, Matsui H
Mitigation of Irradiation Embrittlement by Annealing
Amayev AD, Kryukov AM, Levit VI, Platonov PA, Sokolov MA
Microstructure and Mechanical Properties of WWER-440 Reactor Vessel Metal After Service Life Expiration and Recovery Anneal
Gorynin IV, Nesterova EV, Nikolaev VA, Rybin VV
A Microstructural Study of Phosphorus Segregation and Intergranular Fracture in Neutron Irradiated Submerged-Arc Welds
Bischler PJE, Wild RK
Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Ccopper Weld Metal
Iskander SK, Sokolov MA, Nanstad RK
In-Service Embrittlement of the Pressure Vessel Welds at the Doel I And II Nuclear Power Plants
Gérard R, Fabry A, Van de Velde J, Puzzolante J-L, Verstrepen A, Van Ransbeeck T, Van Walle E
The Toughness of Irradiated Pressure Water Reactor (PWR) Vessel Shell Rings and the Effect of Segregation Zones
Bethmont M, Frund J-M, Housin B, Soulat P
Low Temperature Embrittlement of RPV Support Structure Steel
Boydon FMD, McElroy RJ, Gage G, Phythian WJ
Effects of Neutron Flux and Irradiation Temperature on Irradiation Embrittlement of A533B Steels
Suzuki M, Onizawa K, Kizaki M
The Interpretation of Charpy Impact Test Data Using Hyper-Logistic Fitting Functions
Helm JL
Uncertainty Evaluation in Transition Temperature Measurements
Brillaud C, Augendre H, Bethmont M
On Impact Testing of Subsize Charpy V-Notch Type Specimens
Sokolov MA, Nanstad RK
Reconstitution: Where Do We Stand?
van Walle E
The Reconstitution of Charpy-Size Tensile Specimens
Van Ransbeeck T, Van Walle E, Fabry A, Puzzolante JL, Van de Velde J
Notch Reorientation of Charpy-V Specimens of the BWR Philippsburg 1 Through Reconstitution
van Walle E, Fabry A, Van Ransbeeck T, Puzzolante J-L, Van de Velde J, Tulke K, Backfisch W
Variations in Charpy Impact Data Evaluated by a Round-Robin Testing Program A Summary
Lowe AL
The Embrittlement Data Base (EDB) and Its Applications
Wang JA, Kam FBK, Stallmann FW
Surveillance Programme for WWER-440/Type 213 Reactor Pressure Vessels- Standard Programme, Re-Evaluation of Results, Supplementary Programme
Brumovský M, Novosad P, d'árek J
Application of Micromechanical Models of Ductile Fracture Initiation to Reactor Pressure Vessel Materials
Chaouadi R, De Meester P, van Walle E, Fabry A, Van de Velde J
On the Effect of Flux and Composition on Irradiation Hardening at 60°C
Odette GR, Lucas GE, Klingensmith RD, Stoller RE
The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature
Jones RB, Williams TJ
HFIR Steels Embrittlement: The Possible Effect of Gamma Field Contribution
Remec I, Wang >J-A, Kam FBK
The Influence of Metallurgical Variables on the Temperature Dependence of Irradiation Hardening in Pressure Vessel Steels
Odette GR, Lucas GE, Klingensmith RD
Effects of Proton Irradiation on Positron Annihilation and Micro-Vickers Hardness of Fe-C-Cu Model Alloys
Shibamoto H, Koyama K, Yuya H, Hasegawa M, Kimura A, Matsui H, Yamaguchi S
Ductile Fracture Mechanisms in an A302B Modified Reactor Pressure Vessel Steel
Cuddy LJ, Manahan MP, Brauer G, Martinko J
Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials
DeVan MJ, Lowe AL, Hall JB
The Effect of Constraint on Toughness of a Pressure Vessel Steel
Edsinger K, Odette GR, Lucas GE, Wirth B
The Effects of Thermal Annealing on Fracture Toughness of Low Upper-Shelf Welds
Sokolov MA, Nanstad RK, Iskander SK
Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction
Wirth B, Edsinger K, Odette GR, Lucas GE
The Microstructural Stability and Mechanical Properties of Two Low Activation Martensitic Steels
Victoria M, Batawi E, Briguet C, Gavillet D, Marmy P, Peters J, Rézai-Aria F
Influence of Thermomechanical Treatment on Irradiation Microstructures in an ODS Ferritic Steel
Little EA
Effect of Boron on Post Irradiation Tensile Properties of Reduced Activation Ferritic Steel (F-82H) Irradiated in HFIR
Shiba K, Suzuki M, Hishinuma A, Pawel JE
Irradiation Effects on Base Metal and Welds of 9Cr-1Mo (EM10) Martensitic Steel
Alamo A, Séran JL, Rabouille O, Brachet JC, Maillard A, Touron H, Royer J
Evaluation of the Upper Shelf Energy for Ferritic Steels from Miniaturized Charpy Specimen Data
Kurishita H, Shibahara I, Narui M, Mizuta S, Kayano H
On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels
Lucas GE, Odette GR, Edsinger K, Wirth B, Sheckherd JW
Microstructural Evolution of Austenitic Stainless Steels Irradiated in a Fast Reactor
Borodin OV, Bryk VV, Voyevodin VN, Neklyudov IM, Shamardin VK, Neystroev VS
Effects of Helium/DPA Ratio, Alloy Composition and Cold Work on Microstructural Evolution and Hardening of Ni-Doped Fe-Cr-Ni Alloys Neutron-Irradiated at 465°C
Kawanishi H, Hamilton ML, Garner FA
Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor
Shamardin VK, Neustroev VS, Povstyanko AV, Bulanova TM, Ostrovsky ZE, Kuznetzov AA, Kursevitch IP, Nikolaev VA
Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels
Shibahara I, Akasaka N, Onose S
On the Fundamentals of Radiation Damage in FCC Materials, A Review
Schüle W
An Investigation of Microstructures and Yield Strengths in Irradiated Austenitic Stainless Steels Using Small Specimen Techniques
Toloczko MB, Lucas GE, Odette GR, Stoller RE, Hamilton ML
Irradiation Hardening and Loss of Ductility of Type 316L(N) Stainless Steel Plate Material Due to Neutron-Irradiation
Horsten MG, de Vries MI
Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel
Jitsukawa S, Hishinuma A, Suzuki M
Fracture Toughness of Irradiated Candidate Materials for ITER First Wall/Blanket Structures
Alexander DJ, Pawel JE, Grossbeck ML, Rowcliffe AF, Shiba K
Irradiation Behavior of Weldments of Austenitic Stainless Steel Made by Various Welding Techniques
Shiba K, Sawai T, Jitsukawa S, Hishinuma A, Pawel JE
Helium Effects on the Reweldability and Low Cycle Fatigue Properties of Welded Joints for Type Cr16Ni11Mo3Ti and 316L(N) Stainless Steels
Fabritsiev SA, van der Laan JG
Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals
Tavassoli A-A, Picker C, Wareing J
Bubble Microstructure Evolution and Helium Behavior in He Implanted Ni-Base Alloys
Kalin BA, Chernov II, Kalashnikov AN, Solovyev BG
Saturation of Swelling in Neutron Irradiated Pure Nickel and Its Dependence on Temperature and Starting Dislocation Microstructure
Stubbins JF, Garner FA
Effect of Irradiation in a Spallation Neutron Environment on Tensile Properties and Microstructure of Aluminum Alloys 5052 and 6061
Dunlap JA, Borden MJ, Sommer WF, Stubbins JF
Correlation Between Shear Punch and Tensile Data for Neutron-Irradiated Aluminum Alloys
Hamilton ML, Toloczko MB, Edwards DJ, Sommer WF, Borden MJ, Dunlap JA, Stubbins JF, Lucas GE
Effect of Dynamically Charged Helium on Mechanical Properties of Vanadium-Base Alloys
Chung HM, Loomis BA, Smith DL
Swelling and Structure of Vanadium-Base Alloys Irradiated in the Dynamic Helium Charging Experiment
Chung HM, Loomis BA, Smith DL
Corrosion Response of Pre-Irradiated Zr-2.5Nb Pressure Tube Material
Urbanic VF, Griffiths M
The Development of Structural Materials for Reduced Long-Term Activation
Ehrlich K, Cierjacks SW, Kelzenberg S, Möslang A
Characterization of Irradiation-Induced Precipitates by Small Angle X-Ray and Neutron Scattering Experiments
Groe M, Eichhorn F, Böhmert J, Brauer G
Variable Energy Positron Measurements at Nitrogen Ion Bombarded Steel Surfaces
Brauer G, Kolitsch A, Schut H, van Veen A
Use of Laser Extensometer for Mechanical Tests on Irradiated Materials
Brillaud C, Meylogan T, Salathe P
Author Index
Subject Index
Committee: E10
Paper ID: STP1270-EB
DOI: 10.1520/STP1270-EB
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STP1270-EB
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