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Digital Library / STP / STP1325-EB
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Effects of Radiation on Materials: 18th International Symposium
Nanstad RK
Pages: 1120
Published: 1999
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Table of Contents
Irradiation Creep in Nickel Containing and in Manganese Containing Stainless Steel Alloys
Hausen H, Schüle W
Irradiation Hardening of Pressure Vessel Steels at 60°C: The Role of Thermal Neutrons and Boron
Odette GR, Lucas GE, Klingensmith D
The Impact of Mobile Point Defect Clusters in a Kinetic Model of Pressure Vessel Embrittlement
Stoller RE
An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper, Phosphorus and Nickel Additions
Buswell JT, Little EA, Sinclair RN
An Assessment of Potential Gamma Ray Enhancement of Embrittlement in ABWR Pressure Vessel Walls
Garner FA, Greenwood LR, Roy P
Dynamic Finite Element Modeling of the Upper Shelf Energy of Precracked Charpy Specimens of Neutron Irradiated Weld Metal 72W
Kumar AS, Sidener SE, Hamilton ML
Anomalous Hardening in Model Alloys and Steels Thermally Aged at 290°C and 350°C: Implications to Low Flux Irradiation Embrittlement
Odette GR, Lucas GE, Klingensmith D
Small Angle Neutron Scattering Study of Linde 80 RPV Welds
Wirth BD, Odette GR, Pavinich WA, Lucas GE, Spooner SE
Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70
Nanstad RK, McCabe DE, Swain RL
Fracture Toughness Testing of Linde 1092 Reactor Vessel Welds in the Transition Range Using Charpy-Sized Specimens
Pavinich WA, Yoon KK, Hour KY, Hoffman CL
Comparison of Irradiation-Induced Shifts of K and Charpy Impact Toughness for Reactor Pressure Vessel Steels
Sokolov MA, Nanstad RK
Miniaturized Charpy Test for Reactor Pressure Vessel Embrittlement Characterization
Manahan MP
Use of Forces from Instrumented Charpy V-Notch Testing to Determine Crack-Arrest Toughness
Iskander SK, Nanstad RK, Sokolov MA, McCabe DE, Hutton JT, Thomas DL
The Ductile-Brittle Transition Behaviour of Submerged-Arc Weldments Following High Temperature Exposure
Beere WB, Fidler RS, Bolton CJ, Fenton ST, Jones RB
Irradiation of Vessel Materials Using KORPUS Facility of RBT-6 Reactor
Golovanov VN, Markina NV, Raetsky VM, Seriodkin SV, Tsykanov VA
Auger Spectroscopy of Magnox Pressure Vessel Steels
Fisher S, Knowles G, Lee B
Phosphorus Free Energy Change Associated with Segregation to Grain Boundaries in Submerged-Arc Welds
Mendes CM
Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening
Gurovich BA, Korolev YN, Kuleshova EA, Nikolaev YA, Shtrombakh YI
Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels
McElroy RJ, English CA, Foreman AJ, Gage G, Hyde JM, Ray PHN, Vatter IA
The Effect of Heat Treatment on Phosphorus Segregation in a Submerged-Arc Weld Metal
Beere WB, Buswell JT
SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions
Sokolov MA, Spooner S, Odette GR, Wirth BD, Lucas GE
Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals after Irradiation and Annealing
Große M, Nitzsche P, Böhmert J, Brauer G
Hardness and Microstructural Response to Thermal Annealing of Irradiated ASTM A533B Class 1 Plate Steel
Reinhart DE, Kumar AS, Gelles DS, Hamilton ML, Rosinski ST
Effects of Damage Rate on Irradiation Hardening and Post-irradiation Annealing Characteristics of Carbon Steel
Suzuki M, Idei Y, Kizaki M, Onizawa K
Experimental Tests of Irradiation-Anneal-Reirradiation Effects on Mechanical Properties of RPV Plate and Weld Materials
Rosinski ST, Hawthorne JR, Rochau GE
Comparison of Different Experimental and Analytical Measures of the Thermal Annealing Response of Neutron-Irradiated RPV Steels
Iskander SK, Sokolov MA, Nanstad RK
The Annealing Recovery of The Palisades Nuclear Power Plant Surveillance Material Using Weld Reconstitution
Williams JF, Kneeland JR, Server WL, Terek E, Lott RG, Friedman EN
Design of an Annealing Supplemental Surveillance Program for the Palisades Reactor Pressure Vessel
Server WL, Lott RG, Kneeland JR, Hanson JL
Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel
Fabry A, Chaouadi R, Puzzolante JL, Van de Velde J, Biemiller EC, Rosinski ST, Carter RG
Role and Experience with Thermal Monitors in Reactor Vessel Surveillance Capsules
Lowe AL
A Consideration of Scatter in Radiation Damage Trend Curves for Reactor Pressure Vessel Steel Plate Materials
Griesbach TJ, Server WL
Refinements to Pressure Vessel Steel Embrittlement Correlations
Byrne ST, Hardies RO
Development of Embrittlement Prediction Models for U.S. Power Reactors and The Impact of The Heat-Affected Zone to Thermal Annealing
Wang JA
Empirical Correlation of Observed Three Stages of Fast Neutron Irradiation Hardening and Embrittlement in WWER-440 Pressure Vessel Materials
Levit VI, Korolev YuN, Tipping Ph, Lessa RNT
Evaluation of Irradiated Pressure Vessel Steel by Mechanical Tests and Positron Annihilation Lineshape Analysis
Nakamura N, Ohta Y, Yoshida K, Maeda N
Detection of Radiation Damage in Low Alloy Steel Using a Squid Sensor
Otaka M, Shimizu S, Morinaka R, Maeda N, Yamaguchi A
Nondestructive Evaluation of Neutron Irradiation Embrittlement for Reactor Vessel Steel by Magnetomechanical Acoustic Emission Technique
Maeda N, Yamaguchi A, Saito K, Hirasawa T, Komura I, Chujou N
Changes in Electromagnetic Properties of a Low-Alloy Steel Caused by Neutron Irradiation
Goto T, Kamimura T, Kumano S, Takeuchi I, Maeda N, Yamaguchi A
Detection of Irradiation Embrittlement of Low-Alloy Steel for Nuclear Reactor Pressure Vessels Using a Probe Type Eddy Current Sensor
Maeda N, Yamaguchi A, Sugibayashi T, Kohno K
The Effect of Ordering on Radiation-Induced Segregation in Austenitic Iron- and Nickel-Base Alloys
Allen TR, Was GS
The Modelling of Combined Radiation-Induced and Thermal Non-Equilibrium Segregation of Chromium in Neutron-Irradiated Austenitic Stainless Steels
Goodwin CC, Faulkner RG, Fisher SB
Radiation-Induced Instability of MnS Precipitates and its Possible Consequences on Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels
Chung HM, Sanecki JE, Garner FA
Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Held Joints after Neutron Irradiation
Shiba K, Ioka I, Jitsukawa S, Hamada S, Hishinuma A, Robertson JP
Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel after Low Temperature Neutron Irradiation
Robertson JP, Ioka I, Rowcliffe AF, Grossbeck ML, Jitsukawa S
Microstructures in Neutron Irradiated Fe-Cr-Ni-P-Ti Model Austenitic Alloys Doped with B
Muroga T, Watanabe H, Yoshida N, Kurishita H
Behavior of Fe-Cr-Ni-xP-yTi Alloys under Electron/He Ion Dual Beam Irradiation
Takahashi H, Tsuchida H, Hidaka Y, Kinoshita H, Watanabe S
Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR
Garner FA, Toloczko MB, Munro B, Adaway S, Standring J
Irradiation Creep at Temperatures of 400°C and Below for Application to Near-Term Fusion Devices
Grossbeck ML, Gibson LT, Jitsukawa S, Mansur LK, Turner LJ
Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400600°C
Toloczko MB, Garner FA
Evaluation of Low-Temperature Swelling in Austenitic Stainless Steels
Katoh Y
A Reevaluation of Helium/dpa and Hydrogen/dpa Ratios for Fast Reactor and Thermal Reactor Data Used in Fission-Fusion Correlations
Garner FA, Greenwood LR, Oliver BM
The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation
Ukai S, Akasaka N, Hattori K, Onose S
The Dependence of Swelling on Phosphorus Content in Stainless Steels Containing High Silicon Levels
Reinhart DE, Garner FA
Neutron Irradiation Creep at 100°C on 316L, AMCR, and Welded 316L Stainless Steel Alloys
Hausen H, Schüle W
Effect of Radiation-Induced Segregation on Precipitate Stability and Swelling in Irradiated Alloys
Pechenkin VA, Epov GA, Stepanov IA, Konobeev YV
Microstructural and Microchemical Characterisation of Ferritic Ex-Service Magnox Control Rod Sheath Material
Walmsley J, Fisher S, Spellward P
Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix
Dubuisson P, Schill R, Hugon M-P, Grislin I, Séran J-L
The Consequences of Helium Production and Nickel Additions on Microstructural Development in Isotopically Tailored Ferritic Alloys
Gelles DS
Tensile and Charpy Impact Properties of Irradiated Reduced Activation Ferritic Steels
Klueh RL, Alexander DJ
Impact Behavior of Low Activation Steels at 30 dpa
Hamilton ML, Schubert LE, Gelles DS
Electron Microscopy of Precipitation and Age Hardening in Fe-0.6Cu Model Alloy
Kawanishi H, Suzuki M
Brazed Dispersion Strengthened Copper: The Effect of Neutron Irradiation and Transmutation on Bond Integrity
Edwards DJ, Hamilton ML, Garner FA, Samal P, Troxell JD
Void Swelling of Copper and Copper Alloys Induced by Heavy Ion Irradiation
Muroga T, Matue T, Watanabe H, Yoshida N
Radiation-Enhanced Diffusion of Ni in Nickel and in Copper
Schüle W
The Effects of Irradiation on the Mechanical Properties of 6061-T651 Aluminum Base Metal and Weldments
Alexander DJ
Irradiation Induced Growth and Microstructure Evolution of Zr-1.2Sn-1Nb-0.4Fe Under Neutron Irradiation to High Doses
Nikulina AV, Shishov VN, Peregud MM, Tselischev AV, Shamardin VK, Kobylyansky GP
The Neutron Irradiation Effect on the Mechanical Properties and Structure of Beryllium
Fabritsiev SA, Pokrovsky AS, Bagautdinov RM
In-Situ Radio-Luminescence from Sapphires Under Fission Reactor Irradiation
Shikama T, Kakuta T, Narui M, Sagawa T, Jensen BFH, Nakazawa S, Kayano H
The Effects of Constraint, Loading Rate and Irradiation on the Toughness-Temperature Behavior of a V-4Cr-4Ti Alloy
Odette GR, Donahue E, Lucas GE, Sheckherd JW
Effects of Helium on Void Swelling Behavior of Vanadium Alloys Using Dual Ion Beam Irradiation
Iwai T, Sekimura N, Garner FA
Effects of Low Temperature Irradiation on the Mechanical Properties of V-4Cr-4Ti
Alexander DJ, Snead LL, Zinkle SJ, Gubbi AN, Rowcliffe AF, Eatherly WS, Bloom EE
Author Index
Subject Index
Committee: E10
Paper ID: STP1325-EB
DOI: 10.1520/STP1325-EB
 ASTM International is a member of CrossRef.
0-8031-2614-X
978-0-8031-2614-5
STP1325-EB
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