STP782

    Effects of Radiation on Materials

    Brager HR, Perrin JS
    Published: 1982


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    This publication is divided into five major subject areas: Creep and Swelling; Microstructural Development; Pressure Vessel Steels; Mechanical Properties; Charged Particle Irradiation; Theory of Radiation Effects.


    Table of Contents

    Introduction
    Brager H.

    The Swelling of Solution Annealed 316 Cladding in Rapsodie and Phenix
    Dupouy J., Seran J.

    The Swelling Behavior of 20% CW 316 Stainless Steel Cladding Irradiated With and Without Adjacent Fuel
    Bates J., Jost J., Makenas B.

    Interdependence of In-Pile Creep and Void Swelling in Ti- and Nb-Stabilized Stainless Steels
    Ehrlich K., Herschbach K., Schneider W.

    Initial Results of Swelling and Irradiation Creep Interaction Testing
    Foster J.

    Creep and Swelling of Type 348 Stainless Steel at Temperatures up to 700 K and Comparison with Fast Reactor Data
    Beeston J., Thomas L.

    Effect of Preinjected Helium on Swelling and Microstructure of Neutron Irradiated Pressurized Tubes of Type 316 Stainless Steel
    Bloom E., Hishinuma A., Horak J., Vitek J.

    An In-Reactor Creep Correlation for 20% Cold Worked AISI 316 Stainless Steel
    Chin B., Gilbert E., Puigh R.

    Analysis of the High Fluence Creep Behavior of Two Precipitation Strengthened Alloys
    Chin B., Puigh R.

    Microstructural Changes in Neutron-Irradiated Commercial Alloys: A Sequel
    Bell W., Lauritzen T.

    The Influence of Cold Work Level, Solute and Helium Content on the Swelling of “Pure” AISI 316 (Fe-17Cr-16.7Ni-2.5Mo)
    Brager H., Garner F.

    Precipitation in Irradiated and Unirradiated Austenitic Steels
    Williams T.

    Relationship Between Phase Development and Swelling of AISI 316 During Temperature Changes
    Garner F., Yang W.

    Microstructural Stability of Fast Reactor Irradiated 10–12%Cr Ferritic-Martensitic Stainless Steels
    Little E., Stoter L.

    Dislocation Substructure in Zirconium Alloys Irradiated in EBR-II
    Fidleris V., Gilbert R., Holt R.

    The Effect of Preimplanted Helium on the Microstructure of Neutron Irradiated Nb, Nb-1%Zr and Nb-1%Zr-0.4%Mo
    Elen J., Mastenbroek A., van Tilborg P., van Witzenburg W.

    Swelling in Neutron Irradiated Titanium Alloys
    Peterson D.

    The Effect of Helium on Swelling in Stainless Steel: Influence of Cavity Density and Morphology
    Odette G., Stoller R.

    History Dependence and Consequences of the Microchemical Evolution of AISI 316
    Garner F., Porter D.

    Influence of Dose and Dose Rate Ont the Microstructure of Solution Annealed 316 Steel Irradiated Around 600 °C
    Le Naour L., Levy V., Vouillon N.

    Microstructure and Tensile Properties of Neutron-Irradiated (Fe0.61Ni0.39)3V Ordered Alloy
    Braski D.

    The Influence of Neutron Exposure, Chemical Composition and Metallurgical Condition, on the Irradiation Shift of Reactor Pressure Vessel Steels
    Austin M., Berrisford R., Squires R., Thomas A., Venables J., Williams T.

    Significance of Nickel and Copper Content to Radiation Sensitivity and Postirradiation Heat Treatment Recovery of Reactor Vessel Steels
    Hawthorne J.

    Radiation Embrittlement of PWR Reactor Vessel Weld Metals : Nickel and Copper Synergism Effects
    Brasseur D., Gros D., Guionnet C., Houssin B., Lefort A., Perdreau R.

    Comparative Irradiation Study of Reactor Pressure-Vessel Steel Weld Metals
    Gerscha A., Hofmann G., Leitz C., Strobel H.

    Evaluation of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation
    Davies L., Ingham T., Squires R.

    Analysis of Fracture Surfaces of Reactor Pressure-Vessel Steels
    deHodgins O., Shriver B.

    The Effect of Accelerated Irradiation on Fracture Behaviour
    Charnock W., Priest R., Stewart A.

    Analytic Predictions of Embrittlement of SA 533 B Pressure Vessel Steels
    Hicks D., Main A., Shriver B.

    Kinetics of Annealing of Irradiated Surveillance Pressure Vessel Steel
    Harvey D., Wechsler M.

    Irradiation Experiments in the Testing Nuclear Power Plant Vak
    Anders D., Föhl J., Leitz C.

    Effects of Neutron Irradiation and Temperature on High Strain Rate Behaviour of Reactor Pressure Vessel Steel
    Bílek Z., Buchar J., Dušek F.

    A Single Specimen Method for Determining Upper Shelf Fracture Toughness Shifts Using Precracked Charpy Specimens
    Futato R., Lowe A., Neale B., Pavinich W., Van Der Sluys W.

    Preparation of Reconstituted Charpy V-Notch Impact Specimens for Generating Pressure Vessel Steel Fracture Toughness Data
    Fromm E., McConnell P., Perrin J., Server W.

    Low Dose Irradiation Effects of Heat-to-Heat Variation of Type 304 Stainless Steel Creep and Tensile Properties
    van der Schaaf B.

    Irradiation Embrittlement in Some Austenitic Superalloys
    Bell W., Lauritzen T., Vaidyanathan S.

    Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel
    Cannon N., Hamilton M., Johnson G.

    Nickel-Doped Ferritic (Martensitic) Steels for Fusion Reactor Irradiation Studies: Tempering Behavior and Unirradiated and Irradiated Tensile Properties
    Grossbeck M., Klueh R., Vitek J.

    Effects of Temperature and Strain Rate on the Low Cycle Fatigue Properties of Neutron Irradiated Stainless Steel DIN 1.4948
    de Vries M.

    Deformation Microstructure Developed During Fatigue Crack Propagation in Type 316 Stainless Steel at 593°C
    Michel D., Smith H.

    Effects of Fast Neutron Irradiation on the Fracture Behavior of Stainless Steel
    Fish R., Huang F.

    Fatigue Crack Growth of Low-Fluence Neutron-Irradiated Stainless Steel DIN 1.4948
    de Vries M.

    The Influence of Neutron Irradiation on the Properties of Beryllium
    Fleck R.

    A Comparison of Transient-Heating Burst Test Results of Unirradiated and Irradiated Zircaloy-4 Fuel Rod Cladding
    Lowry L., Perrin J.

    Effects of Neutron Irradiation on the Mechanical Properties of a 5154-0 Type Aluminum Alloy
    Dekker F., Lijbrink E., van Grol H., van Witzenburg W.

    On the Possibility of Using Amorphous Metals in High Radiation Environments
    Kesternich W., Lohmann W.

    Annealing of Radiation Damaged Monazite
    Cartz L., Ehlert T., Gowda K., Karioris F.

    Void Swelling of Ferritic Alloys Bombarded with Nickel Ions
    Johnston W., Lauritzen T., Rosolowski J., Turkalo A.

    Void Swelling and Phase Stability in Different Heats of Cold-Drawn Type 1.4970 Stainless Steel After Heavy-Ion Irradiation
    Ehrlich K., Knoblauch G., Vaidya W.

    Irradiation Creep of Dilute Nickel Alloys
    Atkins T., McElroy R.

    Optimization of Precipitation Hardened Fe-Ni-Cr Alloys Using Nickel Ion Bombardment Simulation Studies
    Bajaj R., Bleiberg M., Diamond S.

    Ion Damage in 316 Stainless Steel Over a Broad Dose Range
    Farrell K., Packan N.

    Surface Segregation in Concentrated Ni-Cu Alloys Under Irradiation
    Naundorf V., Rehn L., Wagner W., Wiedersich H.

    The Effect of Nitrogen on Void Swelling of Stainless Steel
    Fujihira T., Igata N., Kohno Y., Tanabe N., Tsunakawa H.

    Mechanical Properties of 800-MeV Proton-Irradiated Metals2
    Brown R., Cost J.

    Damage Profile In Ion-Bombarded Nickel and Stainless Steel
    Aruga T., Hamada S., Shiraishi K., Tanaka M.

    The Effect of Pulse Irradiation on Void Swelling of a “Pure” 316 Stainless Steel
    Igata N., Miyahara K., Packan N.

    Comparison of Neutron and Heavy-Ion Damage in a Single-Phase Austenite
    Farrell K., Packan N.

    Defect Production Rates by Electrons, Ions and Neutrons in Cubic Metals
    Andersen H., Bak J., Coltman R., Guinan M., Jung P., Klabunde C., Knudsen H., Nielsen B., Violet C., Williams J.

    Kinetics of Radiation-Induced Segregation in Ternary Alloys
    Kumar A., Lam N., Wiedersich H.

    Effect of Radiation-Induced Segregation on Void Nucleation
    Si-Almed A., Wolfer W.

    On Radiation-Induced Segregation and the Compositional Dependence of Swelling in Fe-Ni-Cr Alloys
    Garner F., Thomas L., Wolfer W.

    Calculation of Cavity Nucleation Under Irradiation with Continuous Helium Generation
    Parker C., Russell K.

    Hardening of Irradiated Alloys due to the Simultaneous Formation of Vacancy and Interstitial Loops
    Alhajji J., Garner F., Ghoniem N.

    A Model for the Evolution of Network Dislocation Density in Irradiated Metals
    Garner F., Wolfer W.

    Asymmetric Dislocation/Point-Defect Interactions and the Modeling of Void Swelling
    Liu Y., Nichols F.

    Cooperative Effects in Microstructural Evolutions Under Irradiation: Fundamental Aspects
    Martin G., Valentin P.

    Three Mile Island-2: Influence on Commercial Nuclear Power Development
    Taylor J.

    The European Fusion Materials Programme
    Darvas J., Verbeek R.

    Fusion Materials Development in the U.S.
    Conn R.

    Rapsodie and Phenix — The Materials Story
    Dupouy J.

    The U.K. Fast Reactor Materials Programme
    Barnes W., Harries D., Lloyd G., Standring J.

    Index


    Committee: E10

    Paper ID: STP782-EB

    DOI: 10.1520/STP782-EB

    ISBN-EB: 978-0-8031-4846-8

    ISBN-13: 978-0-8031-0753-3

    ASTM International is a member of CrossRef.

    0-8031-0753-6
    978-0-8031-0753-3
    STP782-EB