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    STP1366

    Effects of Radiation on Materials: 19th International Symposium

    Hamilton ML, Kumar AS, Rosinski ST, Grossbeck ML
    Published: 2000


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    STP 1366, the nineteenth volume in this series, examines 90 peer-reviewed papers from the international nuclear community, with the emphasis on advanced materials such as silicon carbide and vanadium alloys. A majority of the papers are devoted to pressure vessel embrittlement and its mitigation. Smaller segments address the issues of light water reactors, fusion reactors, and to a lesser extent, breeder reactors.

    Several emerging issues are also explored, including reduced activation, welding of irradiated materials and damage resulting form high-energy proton beams in accelerator-driven nuclear systems.

    Divided into the following sections:

    • Pressure Vessel Steels--Mechanical Properties

    • Pressure Vessel Welds--Mechanical Properties

    • Pressure Vessel Steels--Segregation and Microstructure

    • Ferritic and Ferritic/Martensitic Steels--Annealing and Reirradiation Behavior

    • Irradiation-Induced Behavior Of Iron, Model Alloys, and Ferritic/Martensitic Alloys

    • Low Activation Ferritic/Martensitic Alloys

    • Irradiation Creep and The Creep-Swelling Relationship

    • Austenitic Alloys--Irradiation-Induced Swelling, Segregation and Microstructure

    • Irradiated Structural Alloys--Welding

    • Experimental Techniques and Facilities

    • Beryllium and Ceramics

    • Other Materials

    This publication will be of interest to research scientists, metallurgists, nuclear engineers, nuclear utilities, nuclear reactor vendors. Also university nuclear engineering and materials sciences departments.


    Table of Contents

    A Comparison of East/West Steels for Pressurized Water Reactors

    Exploratory Test of 288°C Radiation Resistance of Two USSR-Produced Reactor Pressure Vessel Steels

    Analysis of Irradiation Data for A302B and A533B Correlation Monitor Materials

    Comparison of Static and Dynamic Transition Temperature Shifts in VVR Reactor Pressure Vessel Steels

    Effect of Radiation on Material Used for 600MW Chinese Nuclear Power Plant Reactor Pressure Vessel

    Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds — Predicted by ASTM E 900 and Measured

    Neutron Spectrum Effect and Damage Analysis on Pressure Vessel Steel Irradiation Behaviour

    Characterization of the Decommissioned Novovoronesh-1 Pressure Vessel Wall Materials by Through-Wall Trepans

    The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels

    Technical Basis for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity Assessment

    Bias and Precision of To Values Determined Using ASTM Standard E 1921-97 for Nuclear Reactor Pressure Vessel Steels

    Fracture Toughness of the Ni-Modified A302-B Plate of the BR3 Reactor Pressure Vessel

    Application of Master Curve Technology to Biaxial and Shallow Crack Fracture Data for A533B Steels

    Effect of Irradiation on Fracture Toughness in the Transition Range of RPV Steels

    Supplementary Surveillance Program for Reactor Pressure Vessels of VVER-440/V-213C Type Reactors in NPP Dukovany

    Irradiation Behavior of Submerged Arc Welding Materials with Different Copper Content

    Effects of Irradiation on Crack-Arrest Toughness of a Low Upper-Shelf Energy, High-Copper Weld

    Effect of Location of V-Notch on Neutron Irradiation-Induced Shift in DBTT of HAZ of Welded Pressure Vessel Steel

    Fracture Toughness Test Results of Precracked Charpy Specimens of Irradiated 73W Weld Material

    Fracture Toughness of Submerged-Arc Weld Samples from a Decommissioned Magnox Reactor Pressure Vessel: Initial Results

    Effects of Irradiation and Thermal Annealing on Fracture Toughness of the Midland Reactor Weld WF-70

    Irradiation Damage Structure in VVER-440 Steels after Irradiation at Different Temperatures and Post-Irradiation Annealing

    Grain Boundary Phosphorus Segregation under Neutron Irradiation and Aging in 2.25Cr1Mo Steel

    Microstructure of the Neutron Irradiated VVER-type Reactor Pressure Vessel Steels

    Influence of Thermal Neutrons on the Hardening and Embrittlement of Plate Steels

    Radiation-Induced Grain Boundary Segregation of Phosphorus in ASME SA533B Ferritic Pressure Vessel Steel

    Comparison of Observed and Predicted Data on Radiation Induced Grain Boundary Phosphorus Segregation in VVER Type Steels

    Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels

    Annealing of a Low Copper Steel: Hardness, SANS, Atom Probe, and Thermoelectric Power Investigations

    Two-Step Recovery Process of Irradiation Hardening in 1%Ni Doped 9%Cr-2%W Martensitic Steel

    Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels

    Embrittlement, Hardening, and Grain Boundary Composition in an Fe-P-C Alloy after Irradiation or Thermal Aging

    Microstructure and Hardening in Thermally Aged and Neutron-Irradiated Fe-Cu Model Alloy

    Neutron Irradiation Rate Dependence of Damage Structures in Fe-Cu Model Alloys

    Gamma-Radiation Annealing to Mitigate Neutron-Induced Degradation of Both Model and Structural Reactor Materials

    Analysis of Stress-Induced Burgers Vector Anisotropy in Pressurized Tube Specimens of Irradiated Ferritic-Martensitic Steels: JFMS and JLF-1

    An Evaluation of Neutron Energy Spectrum Effects in Iron Based on Molecular Dynamics Displacement Cascade Simulations

    Effects of Neutron Irradiation on Fe-Cu Model Alloys and RPV Steels Probed by Positron Annihilation and Hardness Measurements

    Irradiation Behavior of Ferritic-Martensitic 9–12%Cr Steels

    Mechanical Properties and Microstructure of HFR-Irradiated Ferritic/Martensitic Low-Activation Alloys

    Mechanical Properties of Four 7–9%Cr Reduced Activation Martensitic Steels after 2.5 dpa, 300°C Irradiation

    Evaluation of Ductile-Brittle Transition Behavior of Helium-implanted Reduced Activation 9Cr-2W Martensitic Steel by Small Punch Tests

    Irradiation Creep of Austenitic Steels Irradiated Up to High Damage Dose

    Reanalysis of Swelling and Irradiation Creep Data on 316 Type Stainless Steels Irradiated in the FFTF and Phénix Fast Reactors

    The Relationship Between Swelling and Irradiation Creep in 20% Cold-Worked 316 Stainless Steel

    Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steel 16Cr-15Ni-3Mo-Nb-B Irradiated in the BN-350 Reactor

    Effects of Impurity on Radiation Creep Rate of the Interstitial Solid Solutions

    On the Role of Internal Stresses in Void Denuded Zone Formation Under HVEM-Irradiation of Metals and Alloys Preconditioned by Reactor Exposure

    Creep-Fatigue Response of 20% CW 316 SS Under Irradiation at 60°C

    In-Reactor Creep Regularities of Copper

    The Correlation Between Swelling and Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys

    Effect of IVa and Va Elements on Void Formation in Neutron-Irradiated 316 Stainless Steels

    The Question of Saturation of Void Swelling in Fe-Cr-Ni Austenitic Alloys

    Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation

    Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60

    The Effect of Molybdenum on the Grain Boundary Segregation of Chromium Exhibited by Austenitic Stainless Steels after Neutron Irradiation in a BWR

    Microstructure Modeling of a 316L Stainless Steel Irradiated with Electrons

    Effects of Damage Rate on Formation of Voids and Dislocation Loops in Metals

    Stress-Affected Dislocation Development of Stainless Steel During Neutron Irradiation

    Influence of Silicon or Titanium on the Microstructural Evolution of Fe-Cr-35Ni Alloys Irradiated with Neutrons or Self-Ions

    Void-Induced Swelling and Embrittlement in the Russian EI-847 Stainless Steel at PWR-Relevant End-of-Life Conditions

    Interaction of Void-Induced Phase Instability and Subsequent Void Growth in AISI 304 Stainless Steel

    On the Formation of α-Ferrite in Stainless Steel Alloys

    A Composite Model for Segregation and Microstructural Evolution Under Electron Irradiation

    Stress-Modified Welding of Neutron Irradiated Steels

    Thick Plate Welding of Irradiated Stainless Steel

    Cracks in TIG Welded, Neutron-Irradiated 304 Stainless Steel

    Modeling of Helium Bubble Formation During Welding of Irradiated Stainless Steels

    Effect of Neutron Irradiation on Mechanical Properties of Cn-Alloy/SS316 Joints

    Neutron-Induced Evolution of Mechanical Properties of 20% Cold-Worked 316 Stainless Steel as Observed in Both Miniature Tensile and TEM Shear Punch Specimens

    An Investigation into the Origin and Nature of the Slope and x-axis Intercept of the Shear Punch-Tensile Yield Strength Correlation using Finite Element Analysis

    Thermoelectric Power: A Nondestructive Method for Monitoring Irradiation Effects in Ferritic Steels

    Design of a Dedicated Electron Beam Facility for Material Treatment

    Microstructural Examination of Irradiated Beryllium Pebbles

    Measurement and Calculation of Helium Generation in Beryllium Pebbles Irradiated in EBR-II

    In-situ Electrical Resistivity Measurement of MgO•Al2O3 Coating under Neutron Irradiation

    Effect of Ionizing and Displacive Components of Irradiation on the Structural Transformations in Pyrolitic Boron Nitride Ceramics

    Effect Of Irradiation On Structural Materials In Fusion Reactors

    Helium/Hydrogen Measurements in High-Energy Proton-Irradiated Tungsten

    Amorphization of Solids Irradiated by Fast Neutrons

    Effects of Fast Neutron Irradiation at 80K on Titanium Nickelide

    Irradiation Aging of Aluminum Alloys

    Effect of Ion-Irradiation on Phase Transformation in TiNi Shape Memory Alloys

    Irradiation Growth of Zirconium Alloys at High Neutron Fluences

    Neutron Irradiation Test of Optical Components for Fusion Reactor

    Correlation of Hardening and Microstructure of Tantalum Irradiated with Heavy Ions

    Improvement of Post Irradiation Ductility of V-Ti-Cr-Si Type Alloys Neutron Irradiated Around 400°C

    The Influence of Transmutation and Initial Composition on the Microstructural Evolution of Vanadium and V-Cr-Ti Alloys Irradiated in HFIR

    Neutron Irradiation Induced High Temperature Embrittlement of Pure Copper and High Strength Copper Alloys

    Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel

    Author Index

    Subject Index


    Committee: E10

    DOI: 10.1520/STP1366-EB

    ISBN-EB: 978-0-8031-5419-3

    ISBN-13: 978-0-8031-2852-1

    ASTM International is a member of CrossRef.

    0-8031-2852-5
    978-0-8031-2852-1
    STP1366-EB