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SEDL / STP / STP956-EB
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STP956
Influence of Radiation on Material Properties: 13th International Symposium (Part II)
Garner FA, Henager CH, Igata N
Pages: 800
Published: 1987
Other books in this series
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STP 956 includes: irradiation creep and creep rupture; changes in mechanical properties of alloys; pressure vessel steels; radiation damage in nonmetals; irradiation facilities; and dosimetry of radiation environments.
Table of Contents
Overview
Garner F., Henager C., Igata N.
Radiation-Induced Creep of Aluminum and Copper
Ibragimov S., Aitkhozhin E., Pyatiletov Y.
Cessation of Irradiation Creep in AISI 316 Concurrent with High Levels of Swelling
Porter D., Garner F.
In-Reactor Creep Rupture Behavior of the D19 and 316 Alloys
Puigh R., Hamilton M.
Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X
Wassilew C., Wassilew C., Ehrlich K., Bergmann H.
In-Reactor Deformation of Zr-2.5 wt% Nb Pressure Tubes
Causey A., Fidleris V., MacEwen S., Schulte C.
Light-Ion Irradiation Creep and Hardening of Model Ferritic Alloys
Henager C., Simonen E.
The Ductile-to-Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 dpa
Hu W., Gelles D.
Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 2¼Cr-1Mo Steel for a Nuclear Pressure Vessel
Suzuki M., Fukaya K., Kodaira T., Oku T.
Effects of 14-MeV Neutron Irradiations on Mechanical Properties of Ferritic Steels
Kohyama A., Asano K., Igata N.
Impurity Element Effects on the Toughness of 12 Cr-1 Mo Steel
Rou S., Harrelson K., Wilcox R.
Tensile Properties of Several 800 MeV Proton-Irradiated bcc Metals and Alloys
Brown R., Wechsler M., Tschalär C.
Post-Irradiation Fracture Properties of Precipitation-Strengthened Alloy D21
Huang F.
Mechanical Properties at Low and High Strain Rates of PE 16 Alloys Irradiated to 9.2 dpa
Albertini C., Del Grande A., Montagnani M., Pachera A.
J-Integral Toughness of Low Fluence Neutron-Irradiated Stainless Steel DIN 1.4948
De Vries M.
Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels
De Vries M.
Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation
Hawthorne J., Menke B., Awadalla N., O'Kula K.
Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel
Klueh R., Maziasz P.
Radiation Effects on the Micromechanics of Fatigue Crack Initiation
Naughton T., Ghoniem N., Lin T.
Hydrogen Buildup in Irradiated Type-304 Stainless Steel
Jacobs A.
Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures
Hamilton M., Huang F., Yang W., Garner F.
The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys
Braski D.
Tensile and Fracture Properties of EBR-II-Irradiated V-15Cr-5Ti Containing Helium
Grossbeck M., Horak J.
The Effects of Temperature and Strain Rate on the Properties of (Fe,Ni)3V LRO Alloys
Lin H., Wilcox R., Chin B.
Microstructural Characterization of Submerged Arc Weld Metals
Lawless K., Pavinich W., Lowe A.
Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests
Hiser A.
Comparison of the Effect of Power and Test Reactor Irradiations on the Fracture Properties of Submerged-Arc Welds
Lowe A., Pavinich W.
Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy
Sastry Viswanathan B., Pachur D., Nandedkar R.
Tensile Properties of Irradiated Pressure Vessel Steels
Lucas G., Robert Odette G., Maiti R., Sheckherd J.
Effect of Interstitial Impurities on Fracture Characteristics of A533-B Class 1 Pressure Vessel Steel
Jung Y., Murty K.
Irradiation Embrittlement of Advanced Pressure Vessel Steels
Sivaramakrishnan K., Chatterjee S., Anantharaman S., Viswanathan U., Balakrishnan K., Roy P.
A Comparison Between French Surveillance Program Results and Predictions of Irradiation Embrittlement
Brillaud C., Hedin F., Houssin B.
The Effect of Thermal Annealing on the Fracture Properties of a Submerged-Arc Weld Metal
Pavinich W., Lowe A.
Steel Impurity Element Effects on Postirradiation Properties Recovery by Annealing
Hawthorne J.
A Study of Radiation Induced Voids and Precipitates and Their Annealing Behavior by Small-Angle Neutron Scattering
Ukpong I., Krawitz A., Mildner D., Leighly H.
Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements
Chatterjee S., Anantharaman S., Sivaramakrishnan K., Roy P.
Trend Curve Data Development and Testing
McElroy W., Gold R., Simons R., Roberts J.
Damage Rate and Spectrum Effects in Ferritic Steel ΔNDTT Data
Simons R.
Current Limitations of Trend Curve Analysis for the Prediction of Reactor PV Embrittlement
Gold R., McElroy W.
A Statistical Analysis of Fracture Toughness of Irradiated Low-Alloy Steel Plate and Welds
McGowan J., Nanstad R.
Fission Fragment Damage in Ceramic Nuclear Fuels
Matsui H., Horiki M., Tamaki M., Kirihara T.
Fission Fragment Induced Hardening in Uranium Mononitride
Tamaki M., Matsui H., Kirihara T.
The Assessment of Seal Performance and Lifetime Prediction in a Nuclear Environment
Burnay S., Hitchon J.
The Effects of Radiation on Organic Matrix Waste Forms
Phillips D., Johnson D., Burnay S., Hitchon J.
Hydrogen Control in the Handling, Shipping, and Storage of Wet Radioactive Waste
Henrie J., Flesher D.
Photobleaching Effects on Radiation-Induced Loss for Silica Glass Image Fiber
Hayashi S., Wada Y., Chigusa Y., Fujiwara K., Hattori Y., Matsuda Y.
Irradiation Devices for Reactor Materials: Results Obtained from Irradiated Lithium Aluminate at the OSIRIS Reactor
Lefevre F., Thevenot G., Rasneur B., Botter F.
Irradiation Effects in KAPTON Polyimide Film from 14-MeV Neutrons and Cobalt-60 Gamma Rays
Abe K., Logan C., Saneyoshi K., Clinard F.
Changes in Surface Morphology and Microcrack Initiation in Polymers Under Simultaneous Exposure to Stress and Fast Atom Bombardment
Michael R., Frank S., Stulik D., Dickinson J.
Effect of Gamma Radiation on the Permeability of Opthalmic Preservatives Through Fluorine Surface-Treated Low-Density Polyethylene Bottles
Sparacio D., Amini M.
The Low-Temperature Neutron Irradiation Facility at ORNL
Kerchner H., Coltman R., Klabunde C., Young F.
Irradiation Facilities at the Idaho National Engineering Laboratory
Gupta V., Herring J., Korenke R., Harker Y.
Operating Experience at the Los Alamos Spallation Radiation Effects Facility at LAMPF
Sommer W., Lohmann W., Graf K., Taylor I., Chavez R.
Additional Measurements of the Radiation Environment at the Los Alamos Spallation Radiation Effects Facility at LAMPF
Davidson D., Reedy R., Greenwood L., Sommer W., Wechsler M.
Recent Research in Neutron Dosimetry and Damage Analysis for Materials Irradiations
Greenwood L.
Improvement of Accuracy Assessment in Radiation Damage Predictions
Zijp W., Zsolnay &., Nolthenius H.
Comparison of Calculated Integral Values Using Measured and Calculated Neutron Spectra for Fusion Neutronics Analyses
Sekimoto H.
Measurements of 10B(n,He) Reaction Rates in a Mockup Control Rod in ZPPR
Brumbach S., Collins P., Oliver B.
Spectrum Integrated (n,He) Cross Section Comparison and Least Squares Analysis for 6Li and 10B in Benchmark Fields
Schenter R., Oliver B., Farrar H.
Author Index
Subject Index
Committee: E10
Paper ID: STP956-EB
DOI: 10.1520/STP956-EB
ISBN-EB: 978-0-8031-5017-1
 ASTM International is a member of CrossRef.
0-8031-0963-6
978-0-8031-0963-6
STP956-EB
STP 956
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