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SEDL / STP / STP1325-EB
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STP1325
Effects of Radiation on Materials: 18th International Symposium
Nanstad RK, Hamilton ML, Garner FA, Kumar AE
Pages: 1120
Published: 1999
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Features the most current research from an international body of leading experts on how radiation impacts the microstructure and mechanical properties of a wide range of metals. This comprehensive publication includes 71 peer-reviewed papers organized into the following key areas: • radiation damage mechanisms and modeling in reactor pressure vessel steels • relevant mechanical properties and test techniques for pressure vessel steels • grain boundary segregation studies • microstructural aspects of annealing; recovery of properties by thermal annealing • embrittlement correlations • damage characterization using nondestructive techniques • segregation and properties of austenitic alloys • irradiation creep and swelling in structural and austenitic alloys • microstructural studies and mechanical properties experiments on ferritic and ferritic-martensitic alloys • and experiments using copper and copper alloys, vanadium alloys and other materials including aluminum, beryllium, zirconium and sapphire.
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
Klingensmith D., Lucas G., Odette G.
The Impact of Mobile Point Defect Clusters in a Kinetic Model of Pressure Vessel Embrittlement
Stoller R.
An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper, Phosphorus and Nickel Additions
Buswell J., Little E., Sinclair R.
An Assessment of Potential Gamma Ray Enhancement of Embrittlement in ABWR Pressure Vessel Walls
Garner F., Greenwood L., Roy P.
Dynamic Finite Element Modeling of the Upper Shelf Energy of Precracked Charpy Specimens of Neutron Irradiated Weld Metal 72W
Hamilton M., Kumar A., Sidener S.
Anomalous Hardening in Model Alloys and Steels Thermally Aged at 290°C and 350°C: Implications to Low Flux Irradiation Embrittlement
Klingensmith D., Lucas G., Odette G.
Small Angle Neutron Scattering Study of Linde 80 RPV Welds
Lucas G., Odette G., Pavinich W., Spooner S., Wirth B.
Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70
McCabe D., Nanstad R., Swain R.
Fracture Toughness Testing of Linde 1092 Reactor Vessel Welds in the Transition Range Using Charpy-Sized Specimens
Hoffman C., Hour K., Pavinich W., Yoon K.
Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels
Nanstad R., Sokolov M.
Miniaturized Charpy Test for Reactor Pressure Vessel Embrittlement Characterization
Manahan M.
Use of Forces from Instrumented Charpy V-Notch Testing to Determine Crack-Arrest Toughness
Hutton J., Iskander S., McCabe D., Nanstad R., Sokolov M., Thomas D.
The Ductile-Brittle Transition Behaviour of Submerged-Arc Weldments Following High Temperature Exposure
Beere W., Bolton C., Fenton S., Fidler R., Jones R.
Irradiation of Vessel Materials Using KORPUS Facility of RBT-6 Reactor
Golovanov V., Markina N., Raetsky V., Seriodkin S., Tsykanov V.
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 C.
Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms Other than Radiation Hardening
Gurovich B., Korolev Y., Kuleshova E., Nikolaev Y., Shtrombakh Y.
Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels
English C., Foreman A., Gage G., Hyde J., McElroy R., Ray P., Vatter I.
The Effect of Heat Treatment on Phosphorus Segregation in a Submerged-Arc Weld Metal
Beere W., Buswell J.
SANS Study of High-Copper RPV Welds in Irradiated and Annealed Conditions
Lucas G., Odette G., Sokolov M., Spooner S., Wirth B.
Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals after Irradiation and Annealing
Böhmert J., Brauer G., Große M., Nitzsche P.
Hardness and Microstructural Response to Thermal Annealing of Irradiated ASTM A533B Class 1 Plate Steel
Gelles D., Hamilton M., Kumar A., Reinhart D., Rosinski S.
Effects of Damage Rate on Irradiation Hardening and Post-irradiation Annealing Characteristics of Carbon Steel
Idei Y., Kizaki M., Onizawa K., Suzuki M.
Experimental Tests of Irradiation-Anneal-Reirradiation Effects on Mechanical Properties of RPV Plate and Weld Materials
Hawthorne J., Rochau G., Rosinski S.
Comparison of Different Experimental and Analytical Measures of the Thermal Annealing Response of Neutron-Irradiated RPV Steels
Iskander S., Nanstad R., Sokolov M.
The Annealing Recovery of The Palisades Nuclear Power Plant Surveillance Material Using Weld Reconstitution
Friedman E., Kneeland J., Lott R., Server W., Terek E., Williams J.
Design of an Annealing Supplemental Surveillance Program for the Palisades Reactor Pressure Vessel
Hanson J., Kneeland J., Lott R., Server W.
Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel
Biemiller E., Carter R., Chaouadi R., Fabry A., Puzzolante J., Rosinski S., Van de Velde J.
Role and Experience with Thermal Monitors in Reactor Vessel Surveillance Capsules
Lowe A.
A Consideration of Scatter in Radiation Damage Trend Curves for Reactor Pressure Vessel Steel Plate Materials
Griesbach T., Server W.
Refinements to Pressure Vessel Steel Embrittlement Correlations
Byrne S., Hardies R.
Development of Embrittlement Prediction Models for U.S. Power Reactors and The Impact of The Heat-Affected Zone to Thermal Annealing
Wang J.
Empirical Correlation of Observed Three Stages of Fast Neutron Irradiation Hardening and Embrittlement in WWER-440 Pressure Vessel Materials
Korolev Y., Lessa R., Levit V., Tipping P.
Evaluation of Irradiated Pressure Vessel Steel by Mechanical Tests and Positron Annihilation Lineshape Analysis
Maeda N., Nakamura N., Ohta Y., Yoshida K.
Detection of Radiation Damage in Low Alloy Steel Using a Squid Sensor
Maeda N., Morinaka R., Otaka M., Shimizu S., Yamaguchi A.
Nondestructive Evaluation of Neutron Irradiation Embrittlement for Reactor Vessel Steel by Magnetomechanical Acoustic Emission Technique
Chujou N., Hirasawa T., Komura I., Maeda N., Saito K., Yamaguchi A.
Changes in Electromagnetic Properties of a Low-Alloy Steel Caused by Neutron Irradiation
Goto T., Kamimura T., Kumano S., Maeda N., Takeuchi I., Yamaguchi A.
Detection of Irradiation Embrittlement of Low-Alloy Steel for Nuclear Reactor Pressure Vessels Using a Probe Type Eddy Current Sensor
Kohno K., Maeda N., Sugibayashi T., Yamaguchi A.
The Effect of Ordering on Radiation-Induced Segregation in Austenitic Iron- and Nickel-Base Alloys
Allen T., Was G.
The Modelling of Combined Radiation-Induced and Thermal Non-Equilibrium Segregation of Chromium in Neutron-Irradiated Austenitic Stainless Steels
Faulkner R., Fisher S., Goodwin C.
Radiation-Induced Instability of MnS Precipitates and its Possible Consequences on Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels
Chung H., Garner F., Sanecki J.
Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Held Joints after Neutron Irradiation
Hamada S., Hishinuma A., Ioka I., Jitsukawa S., Robertson J., Shiba K.
Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel after Low Temperature Neutron Irradiation
Grossbeck M., Ioka I., Jitsukawa S., Robertson J., Rowcliffe A.
Microstructures in Neutron Irradiated Fe-Cr-Ni-P-Ti Model Austenitic Alloys Doped with 10B
Kurishita H., Muroga T., Watanabe H., Yoshida N.
Behavior of Fe-Cr-Ni-xP-yTi Alloys under Electron/He Ion Dual Beam Irradiation
Hidaka Y., Kinoshita H., Takahashi H., Tsuchida H., Watanabe S.
Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR
Adaway S., Garner F., Munro B., Standring J., Toloczko M.
Irradiation Creep at Temperatures of 400°C and Below for Application to Near-Term Fusion Devices
Gibson L., Grossbeck M., Jitsukawa S., Mansur L., Turner L.
Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400–600°C
Garner F., Toloczko M.
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 F., Greenwood L., Oliver B.
The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation
Akasaka N., Hattori K., Onose S., Ukai S.
The Dependence of Swelling on Phosphorus Content in Stainless Steels Containing High Silicon Levels
Garner F., Reinhart D.
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
Epov G., Konobeev Y., Pechenkin V., Stepanov I.
Microstructural and Microchemical Characterisation of Ferritic Ex-Service Magnox Control Rod Sheath Material
Fisher S., Spellward P., Walmsley J.
Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix
Dubuisson P., Grislin I., Hugon M., Séran J., Schill R.
The Consequences of Helium Production and Nickel Additions on Microstructural Development in Isotopically Tailored Ferritic Alloys
Gelles D.
Tensile and Charpy Impact Properties of Irradiated Reduced Activation Ferritic Steels
Alexander D., Klueh R.
Impact Behavior of Low Activation Steels at 30 dpa
Gelles D., Hamilton M., Schubert L.
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 D., Garner F., Hamilton M., Samal P., Troxell J.
Void Swelling of Copper and Copper Alloys Induced by Heavy Ion Irradiation
Matue T., Muroga T., Watanabe H., Yoshida N.
Radiation-Enhanced Diffusion of 63Ni in Nickel and in Copper
Schüle W.
The Effects of Irradiation on the Mechanical Properties of 6061-T651 Aluminum Base Metal and Weldments
Alexander D.
Irradiation Induced Growth and Microstructure Evolution of Zr-1.2Sn-1Nb-0.4Fe Under Neutron Irradiation to High Doses
Kobylyansky G., Nikulina A., Peregud M., Shamardin V., Shishov V., Tselischev A.
The Neutron Irradiation Effect on the Mechanical Properties and Structure of Beryllium
Bagautdinov R., Fabritsiev S., Pokrovsky A.
In-Situ Radio-Luminescence from Sapphires Under Fission Reactor Irradiation
Jensen B., Kakuta T., Kayano H., Nakazawa S., Narui M., Sagawa T., Shikama T.
The Effects of Constraint, Loading Rate and Irradiation on the Toughness-Temperature Behavior of a V-4Cr-4Ti Alloy
Donahue E., Lucas G., Odette G., Sheckherd J.
Effects of Helium on Void Swelling Behavior of Vanadium Alloys Using Dual Ion Beam Irradiation
Garner F., Iwai T., Sekimura N.
Effects of Low Temperature Irradiation on the Mechanical Properties of V-4Cr-4Ti
Alexander D., Bloom E., Eatherly W., Gubbi A., Rowcliffe A., Snead L., Zinkle S.
Author Index
Subject Index
Committee: E10
Paper ID: STP1325-EB
DOI: 10.1520/STP1325-EB
ISBN-EB: 978-0-8031-5395-0
 ASTM International is a member of CrossRef.
0-8031-2614-X
978-0-8031-2614-5
STP1325-EB
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