STP1270

    Effects of Radiation on Materials: 17th International Symposium

    Gelles DS, Nanstad RK, Kumar AS, Little EA
    Published: 1996


      Format Pages Price  
    PDF (22M) $180   ADD TO CART
    Hardcopy (shipping and handling) $180   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $270.00   ADD TO CART


    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

    ISBN-13: 978-0-8031-2016-7

    ASTM International is a member of CrossRef.

    0-8031-2016-8
    978-0-8031-2016-7
    STP1270-EB