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Digital Library / STP / STP1366-EB
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Effects of Radiation on Materials: 19th International Symposium
Hamilton ML, Kumar AS, Rosinski ST, Grossbeck ML
Pages: 1254
Published: 2000
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Table of Contents
A Comparison of East/West Steels for Pressurized Water Reactors
Davies M, Kryukov A, English C, Nikolaev Y, Server WL
Exploratory Test of 288°C Radiation Resistance of Two USSR-Produced Reactor Pressure Vessel Steels
Hawthorne JR, Sokolov MA, Server WL
Analysis of Irradiation Data for A302B and A533B Correlation Monitor Materials
Wang JA
Comparison of Static and Dynamic Transition Temperature Shifts in VVR Reactor Pressure Vessel Steels
Brumovsky M, Falcnik M, Kytka M, Malek J, Novosad P
Effect of Radiation on Material Used for 600MW Chinese Nuclear Power Plant Reactor Pressure Vessel
Jia X, Xu Y, Yang W, Zhang C
Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds Predicted by ASTM E 900 and Measured
Yoon KK, Pavinich WA
Neutron Spectrum Effect and Damage Analysis on Pressure Vessel Steel Irradiation Behaviour
Pichon C, Brillaud C, Deydier D, Alberman A, Soulat P
Characterization of the Decommissioned Novovoronesh-1 Pressure Vessel Wall Materials by Through-Wall Trepans
Valo MJ, Amaev AD, Ahlstrand R, Chistiakov DA, Krasikov E, Kryukov A, Morosov AM, Nikolaev VA, Platonov P, Rintamaa R, Rybin VV, Shtrombakh Y, Wallin K
The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels
Xu Y, Jia X, Zhang C, Ning G, Yu Q
Technical Basis for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity Assessment
Server WL, Rosinski ST
Bias and Precision of Values Determined Using ASTM Standard E 1921-97 for Nuclear Reactor Pressure Vessel Steels
Kirk M, Lott R, Server WL, Hardies R, Rosinski S
Fracture Toughness of the Ni-Modified A302-B Plate of the BR3 Reactor Pressure Vessel
Chaouadi R, Fabry A, van Walle E, Van de Velde J
Application of Master Curve Technology to Biaxial and Shallow Crack Fracture Data for A533B Steels
Joyce JA, Tregoning RL, Zhang XJ
Effect of Irradiation on Fracture Toughness in the Transition Range of RPV Steels
Onizawa K, Tobita T, Suzuki M
Supplementary Surveillance Program for Reactor Pressure Vessels of VVER-440/V-213C Type Reactors in NPP Dukovany
Brumovsky M, Erben O, Novosad P
Irradiation Behavior of Submerged Arc Welding Materials with Different Copper Content
Langer R, Bartsch R, Nagel G
Effects of Irradiation on Crack-Arrest Toughness of a Low Upper-Shelf Energy, High-Copper Weld
Iskander SK, Nanstad RK, McCabe DE, Swain RL
Effect of Location of V-Notch on Neutron Irradiation-Induced Shift in DBTT of HAZ of Welded Pressure Vessel Steel
Suzuki T, Itoh K, Naruse Y, Matsui H, Kimura A
Fracture Toughness Test Results of Precracked Charpy Specimens of Irradiated 73W Weld Material
Chaouadi R, van Walle E, Fabry A, Scibetta M, Van de Velde J
Fracture Toughness of Submerged-Arc Weld Samples from a Decommissioned Magnox Reactor Pressure Vessel: Initial Results
Bischler PJE, Wootton MR, Bolton CJ
Effects of Irradiation and Thermal Annealing on Fracture Toughness of the Midland Reactor Weld WF-70
McCabe DE, Nanstad RK, Sokolov MA
Irradiation Damage Structure in VVER-440 Steels after Irradiation at Different Temperatures and Post-Irradiation Annealing
Grosse M, Böhmert J
Grain Boundary Phosphorus Segregation under Neutron Irradiation and Aging in 2.25Cr1Mo Steel
Song S, Faulkner RG, Hewitt PEJ, Marmy P, Victoria M
Microstructure of the Neutron Irradiated VVER-type Reactor Pressure Vessel Steels
Koík J, Keilová E, Procházka I, íek J
Influence of Thermal Neutrons on the Hardening and Embrittlement of Plate Steels
Jones RB, Edens DJ, Wootton MR
Radiation-Induced Grain Boundary Segregation of Phosphorus in ASME SA533B Ferritic Pressure Vessel Steel
Meade D, Faulkner RG, Ellis D
Comparison of Observed and Predicted Data on Radiation Induced Grain Boundary Phosphorus Segregation in VVER Type Steels
Nikolaeva AV, Kevorkyan YR, Nikolaev YA
Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels
Sokolov MA, Chernobaeva AA, Nanstad RK, Nikolaev YA, Korolev YN
Annealing of a Low Copper Steel: Hardness, SANS, Atom Probe, and Thermoelectric Power Investigations
Pareige P, Auger P, Welzel S, Van Duysen J-C, Miloudi S
Two-Step Recovery Process of Irradiation Hardening in 1%Ni Doped 9%Cr-2%W Martensitic Steel
Kasada R, Morimura T, Matsui H, Narui M, Kimura A
Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels
Nikolaev YA, Nikolaeva AV
Embrittlement, Hardening, and Grain Boundary Composition in an Fe-P-C Alloy after Irradiation or Thermal Aging
Jones RB, Cowan JR, Corcoran RC, Walmsley JC
Microstructure and Hardening in Thermally Aged and Neutron-Irradiated Fe-Cu Model Alloy
Kawanishi H, Suzuki M
Neutron Irradiation Rate Dependence of Damage Structures in Fe-Cu Model Alloys
Yanagita S, Xu Q, Yoshiie T, Ino H
Gamma-Radiation Annealing to Mitigate Neutron-Induced Degradation of Both Model and Structural Reactor Materials
Karpukhin VI, Krasikov YA, Nikolaenko VA, Shtrombakh YI
Analysis of Stress-Induced Burgers Vector Anisotropy in Pressurized Tube Specimens of Irradiated Ferritic-Martensitic Steels: JFMS and JLF-1
Gelles DS, Kimura A, Shibayama T
An Evaluation of Neutron Energy Spectrum Effects in Iron Based on Molecular Dynamics Displacement Cascade Simulations
Stoller RE, Greenwood LR
Effects of Neutron Irradiation on Fe-Cu Model Alloys and RPV Steels Probed by Positron Annihilation and Hardness Measurements
Hempel A, Saneyasu M, Tang Z, Hasegawa M, Brauer G, Plazaola F, Yamaguchi S, Kano F, Kawai A
Irradiation Behavior of Ferritic-Martensitic 912%Cr Steels
Horsten MG, van Osch EV, Gelles DS, Hamilton ML
Mechanical Properties and Microstructure of HFR-Irradiated Ferritic/Martensitic Low-Activation Alloys
Materna-Morris EI, Rieth M, Ehrlich K
Mechanical Properties of Four 79%Cr Reduced Activation Martensitic Steels after 2.5 dpa, 300°C Irradiation
van Osch E, Horsten M, Lucas GE, Odette GR
Evaluation of Ductile-Brittle Transition Behavior of Helium-implanted Reduced Activation 9Cr-2W Martensitic Steel by Small Punch Tests
Kimura A, Morimura T, Kasada R, Matsui H, Hasegawa A, Abe K
Irradiation Creep of Austenitic Steels Irradiated Up to High Damage Dose
Neustroev VS, Shamardin VK
Reanalysis of Swelling and Irradiation Creep Data on 316 Type Stainless Steels Irradiated in the FFTF and Phénix Fast Reactors
Toloczko MB, Garner FA
The Relationship Between Swelling and Irradiation Creep in 20% Cold-Worked 316 Stainless Steel
Garner FA, Toloczko MB, Puigh RJ
Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steel 16Cr-15Ni-3Mo-Nb-B Irradiated in the BN-350 Reactor
Porollo SI, Vorobjev AN, Konobeev YV, Budylkin NI, Mironova EG, Gamer FA
Effects of Impurity on Radiation Creep Rate of the Interstitial Solid Solutions
Lopuga AD, Pyatiletov YS
On the Role of Internal Stresses in Void Denuded Zone Formation Under HVEM-Irradiation of Metals and Alloys Preconditioned by Reactor Exposure
Konobeev YV, Pechenkin VA, Garner FA
Creep-Fatigue Response of 20% CW 316 SS Under Irradiation at 60°C
Murase Y, Nagakawa J, Yamamoto N, Fukuzawa Y
In-Reactor Creep Regularities of Copper
Aitkhozhin ES, Pyatiletov YS, Chumakov EV
The Correlation Between Swelling and Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys
Allen TR, Busby JT, Gan J, Kenik EA, Was GS
Effect of IVa and Va Elements on Void Formation in Neutron-Irradiated 316 Stainless Steels
Ohnuki S, Yamashita S, Takahashi H, Kato T
The Question of Saturation of Void Swelling in Fe-Cr-Ni Austenitic Alloys
Garner FA, Black CA
Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation
Hübner R, Ehrlich K
Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60
Neustroev VS, Shamardin VK, Ostrovsky ZE, Pecherin AM, Garner FA
The Effect of Molybdenum on the Grain Boundary Segregation of Chromium Exhibited by Austenitic Stainless Steels after Neutron Irradiation in a BWR
Goodwin CC, Faulkner RG, Walmsley JC, Spellward P
Microstructure Modeling of a 316L Stainless Steel Irradiated with Electrons
Henry J, Barbu A, Hardouin-Duparc A
Effects of Damage Rate on Formation of Voids and Dislocation Loops in Metals
Xu Q, Yoshiie T, Iseki M
Stress-Affected Dislocation Development of Stainless Steel During Neutron Irradiation
Porollo SI, Konobeev YV, Kruglov AS, Pevchikh YM, Garner FA
Influence of Silicon or Titanium on the Microstructural Evolution of Fe-Cr-35Ni Alloys Irradiated with Neutrons or Self-Ions
Watanabe H, Garner FA
Void-Induced Swelling and Embrittlement in the Russian EI-847 Stainless Steel at PWR-Relevant End-of-Life Conditions
Garner FA, Porollo SI, Vorobjev AN, Konobeev YV, Dvoriashin AM, Krigan VM, Budylkin NI, Mironova EG
Interaction of Void-Induced Phase Instability and Subsequent Void Growth in AISI 304 Stainless Steel
Porter DL, Garner FA, Bond GM
On the Formation of -Ferrite in Stainless Steel Alloys
Schüle W
A Composite Model for Segregation and Microstructural Evolution Under Electron Irradiation
Watanabe S, Sakaguchi N, Takahashi H, Ohnuki S
Stress-Modified Welding of Neutron Irradiated Steels
Wang C-A, Wikle HC, Grossbeck ML, Chin BA
Thick Plate Welding of Irradiated Stainless Steel
Asano K, Katsura R, Kawano S, Koshiishi M
Cracks in TIG Welded, Neutron-Irradiated 304 Stainless Steel
Kohyama A, Hirose T, Suzuki T, Narui M, Katoh Y
Modeling of Helium Bubble Formation During Welding of Irradiated Stainless Steels
Hashimoto T, Mochizuki M
Effect of Neutron Irradiation on Mechanical Properties of Cn-Alloy/SS316 Joints
Tsuchiya K, Nakamichi M, Kawamura H
Neutron-Induced Evolution of Mechanical Properties of 20% Cold-Worked 316 Stainless Steel as Observed in Both Miniature Tensile and TEM Shear Punch Specimens
Hamilton ML, Garner FA, Hankin GL, Faulkner RG, Toloczko MB
An Investigation into the Origin and Nature of the Slope and x-axis Intercept of the Shear Punch-Tensile Yield Strength Correlation using Finite Element Analysis
Hankin GL, Toloczko MB, Johnson KI, Khaleel MA, Hamilton ML, Garner FA, Davies RW, Faulkner RG
Thermoelectric Power: A Nondestructive Method for Monitoring Irradiation Effects in Ferritic Steels
Miloudi S, Jumel S, Pareige P, Coste J-F, Van Duysen J-C
Design of a Dedicated Electron Beam Facility for Material Treatment
Mittendorfer J
Microstructural Examination of Irradiated Beryllium Pebbles
Gelles DS, Dalle Donne M, Kawamura H, Ohnuki S, Scaffidi-Argentina F
Measurement and Calculation of Helium Generation in Beryllium Pebbles Irradiated in EBR-II
Greenwood LR, Oliver BM, Gelles DS, Baldwin DL, Dalle Donne M, Kawamura H, Scaffidi-Argentina F
In-situ Electrical Resistivity Measurement of MgOAlO Coating under Neutron Irradiation
Nakamichi M, Kawamura H
Effect of Ionizing and Displacive Components of Irradiation on the Structural Transformations in Pyrolitic Boron Nitride Ceramics
Stepanov VA, Stepanov PA, Chernov VM, Golovinov AV, Kryukova LM
Effect Of Irradiation On Structural Materials In Fusion Reactors
Tavassoli F, Burlet H, Lind A, Singh BN, Tähtinen S, van Osch E
Helium/Hydrogen Measurements in High-Energy Proton-Irradiated Tungsten
Oliver BM, Hamilton ML, Garner FA, Sommer WF, Maloy SA, Ferguson PD
Amorphization of Solids Irradiated by Fast Neutrons
Parkhomenko VD, Dubinin SF, Teploukhov SG, Goshchitskii BN
Effects of Fast Neutron Irradiation at 80K on Titanium Nickelide
Dubinin SF, Parkhomenko VD, Teploukhov SG
Irradiation Aging of Aluminum Alloys
Gillemot F, Gillemot L, Uri G
Effect of Ion-Irradiation on Phase Transformation in TiNi Shape Memory Alloys
Matsukawa Y, Sumita Y, Ohnuki S, Watanabe S, Namba C, Takahashi H
Irradiation Growth of Zirconium Alloys at High Neutron Fluences
Shamardin VK, Kobylyansky GP, Kosenkov VM
Neutron Irradiation Test of Optical Components for Fusion Reactor
Ishitsuka E, Sagawa H, Nagashima A, Sugie T, Nishitani T, Yamamoto S, Kawamura H
Correlation of Hardening and Microstructure of Tantalum Irradiated with Heavy Ions
Muroga T, Yasunaga K, Katoh Y, Watanabe H, Yoshida N, Noda N
Improvement of Post Irradiation Ductility of V-Ti-Cr-Si Type Alloys Neutron Irradiated Around 400°C
Satou M, Chuto T, Hasegawa A, Abe K
The Influence of Transmutation and Initial Composition on the Microstructural Evolution of Vanadium and V-Cr-Ti Alloys Irradiated in HFIR
Ohnuki S, Takahashi H, Garner FA
Neutron Irradiation Induced High Temperature Embrittlement of Pure Copper and High Strength Copper Alloys
Fabritsiev SA, Pokrovsky AS, Zinkle SJ, Edwards DJ
Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel
Tähtinen SJ, Pyykkönen MT, Singh BN, Toft P
Author Index
Subject Index
Committee: E10
Paper ID: STP1366-EB
DOI: 10.1520/STP1366-EB
 ASTM International is a member of CrossRef.
0-8031-2852-5
978-0-8031-2852-1
STP1366-EB
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