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SEDL / STP / STP1270-EB
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STP1270
Effects of Radiation on Materials: 17th International Symposium
Gelles DS, Nanstad RK, Kumar AS, Little EA
Pages: 1161
Published: 1996
Other books in this series
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STP 1270 features the latest information from the world's leading experts on how radiation impacts a wide range of metals. This extensive volume includes 68 peer-reviewed papers organized into 8 comprehensive categories: Modeling of Controlling Mechanisms -- 8 papers explore mechanisms controlling the behavior and process of radiation embrittlement and segregation in reactor pressure vessel steel. MicrostructureStudies -- The precipitation process that controls reactor pressure vessel steel embrittlement is discussed in 6 papers. Charpy Impact Response -- 14 papers explore such properties topics as the effects of annealing, irradiated welds and specific reactor parts, consequences of flux, and the use of small specimen technology and reconstitution. Strength and Toughness Issues -- 11 papers expand the mechanical properties data base on reactor pressure vessel steels. Ferritic and Martensitic Steels -- Steels with increased chromium levels for use at higher temperature are examined in 6 papers. Austenitic Steels -- 12 papers present topics including microstructural response, fundamentals of radiation damage and mechanical properties. Other Materials -- Nickel, aluminum alloys, vanadium and a zirconium alloy are the focus of 7 papers. Special Procedures and Techniques -- 4 papers feature procedures for avoiding long term radioactivity and unique methods such as positron measurements and laser extensometry.
Table of Contents
Mechanisms Controlling the Composition Influence on Radiation Hardening and Embrittlement of Iron-Base Alloys
Nikolaev V., Rybin V.
Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering
Stoller R.
The B&W Owners Group Program for Microstructural Characterization and Radiation Embrittlement Modelling of Linde 80 Reactor Vessel Welds
Harbison L., Pavinich W.
Irradiation Embrittlement Modelling of Linde 80 Weld Metals
Lowe A., McElroy R.
Modeling of Irradiation Embrittlement and Annealing/Recovery in Pressure Vessel Steels
Freyer P., Lott R.
The Modelling of Irradiation Embrittlement in Submerged-Arc Welds
Bolton C., Buswell J., Jones R., Moskovic R., Priest R.
The Modelling of Irradiation-Enhanced Phosphorus Segregation in Neutron Irradiated Reactor Pressure Vessel Submerged-Arc Welds
Bolton C., Buswell J., Druce S., English C., Foreman A., Jones R., McElroy R., Vatter I.
Research to Understand the Embrittlement Behavior of Yankee/BR3 Surveillance Plate and Other Outlier RPV Steels
Biemller E., Carter R., Fabry A., Petrova T., Puzzolante J., Van de Velde J., Van Ransbeeck T., Verstrepen A.
Electron Microscopy and Small Angle Neutron Scattering Study of Precipitation in Low Alloy Steel Submerged-Arc Welds
Phythian W., Williams T.
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
Hasegawa M., Kimura A., Matsui H., Shibamoto H., Yamaguchi S., Yuya H.
Mitigation of Irradiation Embrittlement by Annealing
Amayev A., Kryukov A., Levit V., Platonov P., Sokolov M.
Microstructure and Mechanical Properties of WWER-440 Reactor Vessel Metal After Service Life Expiration and Recovery Anneal
Gorynin I., Nesterova E., Nikolaev V., Rybin V.
A Microstructural Study of Phosphorus Segregation and Intergranular Fracture in Neutron Irradiated Submerged-Arc Welds
Bischler P., Wild R.
Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Ccopper Weld Metal
Iskander S., Nanstad R., Sokolov M.
In-Service Embrittlement of the Pressure Vessel Welds at the Doel I And II Nuclear Power Plants
Fabry A., Gérard R., Puzzolante J., Van de Velde J., Van Ransbeeck T., Van Walle E., Verstrepen A.
The Toughness of Irradiated Pressure Water Reactor (PWR) Vessel Shell Rings and the Effect of Segregation Zones
Bethmont M., Frund J., Housin B., Soulat P.
Low Temperature Embrittlement of RPV Support Structure Steel
Boydon F., Gage G., McElroy R., Phythian W.
Effects of Neutron Flux and Irradiation Temperature on Irradiation Embrittlement of A533B Steels
Kizaki M., Onizawa K., Suzuki M.
The Interpretation of Charpy Impact Test Data Using Hyper-Logistic Fitting Functions
Helm J.
Uncertainty Evaluation in Transition Temperature Measurements
Augendre H., Bethmont M., Brillaud C.
On Impact Testing of Subsize Charpy V-Notch Type Specimens
Nanstad R., Sokolov M.
Reconstitution: Where Do We Stand?
van Walle E.
The Reconstitution of Charpy-Size Tensile Specimens
Fabry A., Puzzolante J., Van de Velde J., Van Ransbeeck T., Van Walle E.
Notch Reorientation of Charpy-V Specimens of the BWR Philippsburg 1 Through Reconstitution
Backfisch W., Fabry A., Puzzolante J., Tulke K., Van de Velde J., Van Ransbeeck T., van Walle E.
Variations in Charpy Impact Data Evaluated by a Round-Robin Testing Program — A Summary
Lowe A.
The Embrittlement Data Base (EDB) and Its Applications
Kam F., Stallmann F., Wang J.
Surveillance Programme for WWER-440/Type 213 Reactor Pressure Vessels- Standard Programme, Re-Evaluation of Results, Supplementary Programme
Žd'árek J., Brumovský M., Novosad P.
Application of Micromechanical Models of Ductile Fracture Initiation to Reactor Pressure Vessel Materials
Chaouadi R., De Meester P., Fabry A., Van de Velde J., van Walle E.
On the Effect of Flux and Composition on Irradiation Hardening at 60°C
Klingensmith R., Lucas G., Odette G., Stoller R.
The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature
Jones R., Williams T.
HFIR Steels Embrittlement: The Possible Effect of Gamma Field Contribution
Kam F., Remec I., Wang &.
The Influence of Metallurgical Variables on the Temperature Dependence of Irradiation Hardening in Pressure Vessel Steels
Klingensmith R., Lucas G., Odette G.
Effects of Proton Irradiation on Positron Annihilation and Micro-Vickers Hardness of Fe-C-Cu Model Alloys
Hasegawa M., Kimura A., Koyama K., Matsui H., Shibamoto H., Yamaguchi S., Yuya H.
Ductile Fracture Mechanisms in an A302B Modified Reactor Pressure Vessel Steel
Brauer G., Cuddy L., Manahan M., Martinko J.
Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials
DeVan M., Hall J., Lowe A.
The Effect of Constraint on Toughness of a Pressure Vessel Steel
Edsinger K., Lucas G., Odette G., Wirth B.
The Effects of Thermal Annealing on Fracture Toughness of Low Upper-Shelf Welds
Iskander S., Nanstad R., Sokolov M.
Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction
Edsinger K., Lucas G., Odette G., Wirth B.
The Microstructural Stability and Mechanical Properties of Two Low Activation Martensitic Steels
Batawi E., Briguet C., Gavillet D., Marmy P., Peters J., Rézai-Aria F., Victoria M.
Influence of Thermomechanical Treatment on Irradiation Microstructures in an ODS Ferritic Steel
Little E.
Effect of Boron on Post Irradiation Tensile Properties of Reduced Activation Ferritic Steel (F-82H) Irradiated in HFIR
Hishinuma A., Pawel J., Shiba K., Suzuki M.
Irradiation Effects on Base Metal and Welds of 9Cr-1Mo (EM10) Martensitic Steel
Alamo A., Brachet J., Maillard A., Rabouille O., Royer J., Séran J., Touron H.
Evaluation of the Upper Shelf Energy for Ferritic Steels from Miniaturized Charpy Specimen Data
Kayano H., Kurishita H., Mizuta S., Narui M., Shibahara I.
On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels
Edsinger K., Lucas G., Odette G., Sheckherd J., Wirth B.
Microstructural Evolution of Austenitic Stainless Steels Irradiated in a Fast Reactor
Borodin O., Bryk V., Neklyudov I., Neystroev V., Shamardin V., Voyevodin V.
Effects of Helium/DPA Ratio, Alloy Composition and Cold Work on Microstructural Evolution and Hardening of 59Ni-Doped Fe-Cr-Ni Alloys Neutron-Irradiated at 465°C
Garner F., Hamilton M., Kawanishi H.
Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor
Bulanova T., Kursevitch I., Kuznetzov A., Neustroev V., Nikolaev V., Ostrovsky Z., Povstyanko A., Shamardin V.
Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels
Akasaka N., Onose S., Shibahara I.
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
Hamilton M., Lucas G., Odette G., Stoller R., Toloczko M.
Irradiation Hardening and Loss of Ductility of Type 316L(N) Stainless Steel Plate Material Due to Neutron-Irradiation
de Vries M., Horsten M.
Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel
Hishinuma A., Jitsukawa S., Suzuki M.
Fracture Toughness of Irradiated Candidate Materials for ITER First Wall/Blanket Structures
Alexander D., Grossbeck M., Pawel J., Rowcliffe A., Shiba K.
Irradiation Behavior of Weldments of Austenitic Stainless Steel Made by Various Welding Techniques
Hishinuma A., Jitsukawa S., Pawel J., Sawai T., Shiba K.
Helium Effects on the Reweldability and Low Cycle Fatigue Properties of Welded Joints for Type Cr16Ni11Mo3Ti and 316L(N) Stainless Steels
Fabritsiev S., van der Laan J.
Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals
Picker C., Tavassoli A., Wareing J.
Bubble Microstructure Evolution and Helium Behavior in He+ Implanted Ni-Base Alloys
Chernov I., Kalashnikov A., Kalin B., Solovyev B.
Saturation of Swelling in Neutron Irradiated Pure Nickel and Its Dependence on Temperature and Starting Dislocation Microstructure
Garner F., Stubbins J.
Effect of Irradiation in a Spallation Neutron Environment on Tensile Properties and Microstructure of Aluminum Alloys 5052 and 6061
Borden M., Dunlap J., Sommer W., Stubbins J.
Correlation Between Shear Punch and Tensile Data for Neutron-Irradiated Aluminum Alloys
Borden M., Dunlap J., Edwards D., Hamilton M., Lucas G., Sommer W., Stubbins J., Toloczko M.
Effect of Dynamically Charged Helium on Mechanical Properties of Vanadium-Base Alloys
Chung H., Loomis B., Smith D.
Swelling and Structure of Vanadium-Base Alloys Irradiated in the Dynamic Helium Charging Experiment
Chung H., Loomis B., Smith D.
Corrosion Response of Pre-Irradiated Zr-2.5Nb Pressure Tube Material
Griffiths M., Urbanic V.
The Development of Structural Materials for Reduced Long-Term Activation
Cierjacks S., Ehrlich K., Kelzenberg S., Möslang A.
Characterization of Irradiation-Induced Precipitates by Small Angle X-Ray and Neutron Scattering Experiments
Böhmert J., Brauer G., Eichhorn F., Groe M.
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
ISBN-EB: 978-0-8031-5328-8
 ASTM International is a member of CrossRef.
0-8031-2016-8
978-0-8031-2016-7
STP1270-EB
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