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Digital Library / STP / STP1405-EB
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Effects of Radiation on Materials: 20th International Symposium
Rosinski ST
Pages: 879
Published: 2001
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Table of Contents
Review of Current Recommendations from the Recent IAEA Specialists Meeting on Irradiation Effects on Pressure Vessel Steels and its Mitigation
Davies LM, Server WL, Lyssakov V, Rosinski ST
A Mechanistically-Based Model of Irradiation Damage in Low Alloy Steel Submerged Arc Welds
Williams TJ, Ellis D
Vessel Investigation Program of CHOOZ A PWR Reactor after Shutdown
Brillaud C, Grandjean Y, Saillet S
Development of Reconstitution Technology for Surveillance Specimens in Japan Power Engineering and Inspection Corporation
Kataoka S, Kato N, Taguchi K, Yamamoto M, Oka Y
Master Curve Characterization of Irradiation Embrittlement Using Standard and 1/3-Sized Precracked Charpy Specimens
Lee B-S, Yang W-J, Huh M-Y, Chi S-H, Hong J-H
Radiation Damage Assessment by the Use of Dynamic Toughness Measurements on Pre-Cracked Charpy-V Specimens
Lucon E, Chaouadi R
Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy-v Impact Properties Due to Irradiation and Post-Irradiation Annealing for Japanese A533B-1 Steels
Onizawa K, Suzuki M
Yield and Toughness Transition Predictions for Irradiated Steels Based on Dislocation Mechanics
Wagenhofer M, Gunawardane HP, Natishan ME
Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels
Viehrig H-W, Boehmert J, Dzugan J, Richter H
Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steels and Alloy 718 After Irradiation in High-Energy, Mixed Proton/Neutron Spectrum
Sokolov MA, Robertson JP, Snead LL, Alexander DJ, Ferguson P, James MR, Maloy SA, Sommer WF, Willcutt G, Louthan MR
Review of Phosphorus Segregation and Intergranular Embrittlement in Reactor Pressure Vessel Steels
English CA, Ortner SR, Gage G, Server WL, Rosinski ST
Modeling of Phosphorus Accumulation on Grain Boundaries in Iron Alloys under Irradiation
Pechenkin VA, Stepanov IA, Konobeev YV
Grain Boundary Phosphorus Segregation Under Irradiation and Thermal Aging and Its Effect on the Ductile-to-Brittle Transition
Song S, Faulkner RG, Flewitt PEJ
An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels
Stoller RE, Greenwood LR
Hardness and Microstructure Changes with Thermal Annealing of Neutron-Irradiated Fe-Cu Alloys
Kawanishi H, Suzuki S
Effects of Copper Concentration and Neutron Flux on Irradiation Hardening and Microstructure Evolution in Fe-Cu Model Alloys
Kasada R, Kitao T, Morishita K, Matsui H, Kimura A
Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron Annihilation Techniques
Cumblidge ES, Catchen GL, Motta AT, Brauer G, Böhmert J
Microstructural Evolution in High Nickel Submerged Arc Welds
Hyde JM, Ellis D, English CA, Williams TJ
An Evaluation of the Effect of Radiation Environment on Linde 80 Reactor Vessel Welds
DeVan MJ, Pavinich WA
Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld
Iskander SK, Nanstad RK, Baldwin CA, Heatherly DW, Miller MK, Remec I
Relation Between Resistivity and Mechanical Properties in Heat Affected Zone of Welded Pressure Vessel Steel
Kasada R, Suzuki T, Itoh K, Naruse Y, Kimura A
Fracture Toughness and Tensile Properties of Irradiated Reactor Pressure Vessel Cladding Material
Horsten MG, Belcher WPA
True Characteristics of Strength and Ductility for Neutron-Irradiated Metals and Alloys
Maksimkin OP, Tivanova OV
Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing
Nanstad RK, McCabe DE, Sokolov MA, English CA, Ortner SR
Composition Effects on the Radiation Embrittlement of Iron Alloys
Böhmert J, Ulbricht A, Kryukov A, Nikolaev Y, Erak D
The Determination of Bias Factor Stress Dependence from Experimental Data on Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steels
Konobeev YV, Pechenkin VA, Garner FA
Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II
Cole JI, Allen TR, Tsai H, Ukai S, Mizuta S, Akasaka N, Donomae T, Yoshitake T
Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel
Allen TR, Cole JI, Kenik EA
Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel
Akasaka N, Yamagata I, Ukai S
The Swelling Dependence of Cold Worked 16Cr-15Ni-2Mo-lMn Steel on Neutron Irradiation Temperature, Fluence and Damage Rate During Its Use as a Cladding Material in the BN-600 Reactor
Kozlov AV, Kinev EA, Bryushkova SV, Portnykh IA
Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence
Yoshitake T, Donomae T, Mizuta S, Tsai H, Strain RV, Allen TR, Cole JI
Irradiation Creep Deformation of Modified 316 and 15Cr-20Ni Base Austenitic Fuel Elements Irradiated in FFTF
Uehira A, Ukai S, Mizuta S, Puigh RJ
Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment
Brachet J-C, Averty X, Lamagnère P, Alamo A, Rozenblum F, Raquet O, Bertin J-L
Post-Irradiation Deformation Microstructures in Fe-9Cr
Gelles DS, Hamilton ML, Schäublin R
Effect of Specimen Size on Fatigue Properties of Reduced Activation Ferritic/Martensitic Steel
Hirose T, Sakasegawa H, Kohyama A, Katoh Y, Tanigawa H
Correlation Between Creep Properties and Microstructure of Reduced Activation Ferritic/Martensitic Steels
Sakasegawa H, Hirose T, Kohyama A, Katoh Y, Harada T, Hasegawa T
Comparison of Thermal Creep and Irradiation Creep of HT9 Pressurized Tubes at Test Temperatures from 490°C to 605°C
Toloczko MB, Grambau BR, Garner FA, Abe K
Examination of 304L Stainless Steel to 6061-T6 Aluminum Inertia Welded Transition Joints after Irradiation in a Spallation Neutron Spectrum
Dunn KA, Louthan MR, Mickalonis JI, Maloy S, James MR
Microstructural Alteration of Structural Alloys by Low Temperature Irradiation with High Energy Protons and Spallation Neutrons
Sencer BH, Bond GM, Garner FA, Maloy SA, Sommer WF, James MR
Retention of Very High Levels of Helium and Hydrogen Generated in Various Structural Alloys by 800 MeV Protons and Spallation Neutrons
Oliver BM, Garner FA, Maloy SA, Sommer WF, Ferguson PD, James MR
The Influence of High Energy Proton Irradiation on the Corrosion of Materials
Lillard S, Gac F, Paciotti M, Ferguson P, Willcutt G, Chandler G, Daemen L
The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials Selected for the Target and Blanket Components in the Accelerator Production of Tritium Project
Maloy SA, James MR, Willcutt GJ, Sommer WF, Johnson WR, Louthan MR, Hamilton ML, Garner FA
High-Energy Spallation Neutron Effects on the Tensile Properties of Materials for the Target and Blanket Components for the Accelerator Production of Tritium Project
James MR, Maloy SA, Sommer WF, Johnson WR, Lohmeier DA, Hamilton ML
Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels after Thermal Aging and Neutron Irradiation
Mathon M-H, de Carlan Y, Geoffroy G, Averty X, de Novion C-H, Alamo A
Dimensional Characteristics of Displacement Cascades in Austenitic Steels under Neutron Irradiation at Cryogenic Temperature
Kozlov AV, Portnykh IA, Skryabin LA, Lapin SS
On the +-Phase Boundary in Nickel and in Manganese Containing Stainless Steel Alloys
Schüle W
Effect of Nickel on Irradiation Hardening and Microstructure Evolution of Proton Irradiated Fe-Cu Alloys
Shibamoto H, Kitao T, Matsui H, Hasegawa M, Yamaguchi S, Kimura A
Effect of Final Irradiation Temperature and Frequency of Irradiation Temperature Cycles on Microstructural Evolution of Vanadium Alloys
Nita N, Fukumoto K, Matsui H
Hardening of Vanadium Doped with Nitrogen by Heavy Ion Irradiation and Post-Irradiation Annealing
Nagasaka T, Takahashi H, Muroga T, Yoshida N, Tanabe T
Hydrogen and Helium Gas Formation and their Release Kinetics in Tungsten Rods after Irradiation with 800 MeV Protons
Oliver BM, Garner FA, Hamilton ML, Sommer WF, Maloy SA, Ferguson PD, James MR
The Influence of Temperature, Fluence, Dose Rate, and Helium Production on Defect Accumulation and Swelling in Silicon Carbide
Kishimoto H, Katoh Y, Kohyama A, Ando M
Microstructural Stability of SiC/SiC Composites under Dual-Beam Ion Irradiation
Katoh Y, Kishimoto H, Ando M, Kohyama A, Shibayama T, Takahashi H
Molecular Dynamics Simulation of Radiation Damage Production in Cubic Silicon Carbide
Malerba L, Perlado JM, Pastor I, Diaz de la Rubia T
Influence of the Reactor and Cyclotron Irradiation on Energy Transformation during Plastic Deformation of Metal Materials
Maksimkin OP, Gusev MN
Irradiation-Induced Amorphization and Its Recovery Behavior in Cold-Rolled and Aged Ti-Ni Shape Memory Alloys
Kimura A, Hirose T, Matsui H
Effect of Mass and Energy on Preferential Amorphization in Polycrystalline Silicon Film during Ion Irradiation
Takeda M, Ohnuki S, Suda T, Watanebe S, Abe H, Nashiyama I
Crack Growth Resistance of Irradiated Zr-2.5Nb Pressure Tube Material at Low Hydrogen Levels
Davies PH, Himbeault DD, Shewfelt RSW, Hosbons RR
Author Index
Subject Index
Committee: E10
Paper ID: STP1405-EB
DOI: 10.1520/STP1405-EB
 ASTM International is a member of CrossRef.
0-8031-2878-9
978-0-8031-2878-1
STP1405-EB
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