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Digital Library / STP / STP956-EB
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Influence of Radiation on Material Properties: 13th International Symposium (Part II)
Garner FA
Pages: 800
Published: 1987
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Table of Contents
Overview
Garner FA, Henager CH, Igata N
Radiation-Induced Creep of Aluminum and Copper
Ibragimov SS, Aitkhozhin ES, Pyatiletov YS
Cessation of Irradiation Creep in AISI 316 Concurrent with High Levels of Swelling
Porter DL, Garner FA
In-Reactor Creep Rupture Behavior of the D19 and 316 Alloys
Puigh RJ, Hamilton ML
Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X
Wassilew C, Ehrlich K, Bergmann HJ
In-Reactor Deformation of Zr-2.5 wt% Nb Pressure Tubes
Causey AR, Fidleris V, MacEwen SR, Schulte CW
Light-Ion Irradiation Creep and Hardening of Model Ferritic Alloys
Henager CH, Simonen EP
The Ductile-to-Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 dpa
Hu W-L, Gelles DS
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 SH, Harrelson KJ, Wilcox RC
Tensile Properties of Several 800 MeV Proton-Irradiated bcc Metals and Alloys
Brown RD, Wechsler MS, Tschalär C
Post-Irradiation Fracture Properties of Precipitation-Strengthened Alloy D21
Huang F-H
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
-Integral Toughness of Low Fluence Neutron-Irradiated Stainless Steel DIN 1.4948
De Vries MI
Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels
De Vries MI
Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation
Hawthorne JR, Menke BH, Awadalla NG, O'Kula KR
Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel
Klueh RL, Maziasz PJ
Radiation Effects on the Micromechanics of Fatigue Crack Initiation
Naughton TD, Ghoniem NM, Lin TH
Hydrogen Buildup in Irradiated Type-304 Stainless Steel
Jacobs AJ
Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures
Hamilton ML, Huang F-H, Yang WJS, Garner FA
The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys
Braski DN
Tensile and Fracture Properties of EBR-II-Irradiated V-15Cr-5Ti Containing Helium
Grossbeck ML, Horak JA
The Effects of Temperature and Strain Rate on the Properties of (Fe,Ni)V LRO Alloys
Lin HT, Wilcox RC, Chin BA
Microstructural Characterization of Submerged Arc Weld Metals
Lawless KR, Pavinich WA, Lowe AL
Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests
Hiser AL
Comparison of the Effect of Power and Test Reactor Irradiations on the Fracture Properties of Submerged-Arc Welds
Lowe AL, Pavinich WA
Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy
Sastry Viswanathan B, Pachur D, Nandedkar RV
Tensile Properties of Irradiated Pressure Vessel Steels
Lucas GE, Robert Odette G, Maiti R, Sheckherd JW
Effect of Interstitial Impurities on Fracture Characteristics of A533-B Class 1 Pressure Vessel Steel
Jung YH, Murty KL
Irradiation Embrittlement of Advanced Pressure Vessel Steels
Sivaramakrishnan KS, Chatterjee S, Anantharaman S, Viswanathan UK, Balakrishnan KS, Roy PR
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 WA, Lowe AL
Steel Impurity Element Effects on Postirradiation Properties Recovery by Annealing
Hawthorne JR
A Study of Radiation Induced Voids and Precipitates and Their Annealing Behavior by Small-Angle Neutron Scattering
Ukpong IE, Krawitz AD, Mildner DFR, Leighly HP
Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements
Chatterjee S, Anantharaman S, Sivaramakrishnan KS, Roy PR
Trend Curve Data Development and Testing
McElroy WN, Gold R, Simons RL, Roberts JH
Damage Rate and Spectrum Effects in Ferritic Steel NDTT Data
Simons RL
Current Limitations of Trend Curve Analysis for the Prediction of Reactor PV Embrittlement
Gold R, McElroy WN
A Statistical Analysis of Fracture Toughness of Irradiated Low-Alloy Steel Plate and Welds
McGowan JJ, Nanstad RK
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 SG, Hitchon JW
The Effects of Radiation on Organic Matrix Waste Forms
Phillips DC, Johnson DI, Burnay SG, Hitchon JW
Hydrogen Control in the Handling, Shipping, and Storage of Wet Radioactive Waste
Henrie JO, Flesher DJ
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 CM, Saneyoshi K, Clinard FW
Changes in Surface Morphology and Microcrack Initiation in Polymers Under Simultaneous Exposure to Stress and Fast Atom Bombardment
Michael RS, Frank S, Stulik D, Dickinson JT
Effect of Gamma Radiation on the Permeability of Opthalmic Preservatives Through Fluorine Surface-Treated Low-Density Polyethylene Bottles
Sparacio DA, Amini MA
The Low-Temperature Neutron Irradiation Facility at ORNL
Kerchner HR, Coltman RR, Klabunde CE, Young FW
Irradiation Facilities at the Idaho National Engineering Laboratory
Gupta VP, Herring JS, Korenke RE, Harker YD
Operating Experience at the Los Alamos Spallation Radiation Effects Facility at LAMPF
Sommer WF, Lohmann W, Graf K, Taylor IK, Chavez RM
Additional Measurements of the Radiation Environment at the Los Alamos Spallation Radiation Effects Facility at LAMPF
Davidson DR, Reedy RC, Greenwood LR, Sommer WF, Wechsler MS
Recent Research in Neutron Dosimetry and Damage Analysis for Materials Irradiations
Greenwood LR
Improvement of Accuracy Assessment in Radiation Damage Predictions
Zijp WL, Zsolnay ÉM, Nolthenius HJ
Comparison of Calculated Integral Values Using Measured and Calculated Neutron Spectra for Fusion Neutronics Analyses
Sekimoto H
Measurements of B(,He) Reaction Rates in a Mockup Control Rod in ZPPR
Brumbach SB, Collins PJ, Oliver BM
Spectrum Integrated (,He) Cross Section Comparison and Least Squares Analysis for Li and B in Benchmark Fields
Schenter RE, Oliver BM, Farrar H
Author Index
Subject Index
Committee: E10
Paper ID: STP956-EB
DOI: 10.1520/STP956-EB
 ASTM International is a member of CrossRef.
0-8031-0963-6
978-0-8031-0963-6
STP956-EB
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