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SEDL / STP / STP1046V2-EB
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STP1046V2
Effects of Radiation on Materials: 14th International Symposium (Volume II)
Packan Nicolas, Stoller Roger, Kumar Arvind
Pages: 813
Published: 1990
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Table of Contents
Overview
Kumar A., Packan N., Stoller R.
Effects of 50°C Surveillance and Test Reactor Irradiations on Ferritic Pressure Vessel Steel Embrittlement
Corwin W., Iskander S., Nanstad R., Odette G., Rowcliffe A.
Application of a United Kingdom Magnox Steel Irradiation Model to the HFIR Pressure Vessel
Druce S.
Tensile Properties of Neutron Irradiated A212B Pressure Vessel Steel
Hamilton M., Heinisch H.
Experimental Assessments of Gundremmingen RPV Archival Material for Fluence Rate Effects Studies
Hawthorne J., Hiser A.
Investigation of Materials from a Decommissioned Reactor Pressure Vessel—A Contribution to the Understanding of Irradiation Embrittlement
Föhl J., Kussmaul K., Weissenberg T.
Fine-Scale Microstructural Characterization of Pressure Vessel Steels and Related Materials Using APFIM
Burke M., Miller M.
An Analysis of Small Clusters Formed in Thermally Aged and Irradiated FeCu and FeCuNi Model Alloys
Buswell J., English C., Hetherington M., Phythian W., Smith G., Worrall G.
SANS and DENS Study of Irradiation Damage in a Reactor Pressure Vessel Material with a Systematic Variation of Irradiation Dose and Heat Treatments
Bührer W., Frisius F., Solt G., Waeber W.
Magnetoacoustic and Barkhausen Emission Studies of Neutron Irradiated Iron and Iron-Copper Alloys
Buttle D., Little E., Scruby C.
Precipitation in an Aged Fe-0.85 at%Cu Alloy Observed by Muon Spin Rotation Spectroscopy: A Prospective Method of Studying Irradiation Hardening
Beaven P., Gygax F., Hitti B., Schenck A., Solt G., Tipping P., Waeber W., Zimmermann U.
An Evaluation of Linde 80 Submerged-Arc Weld Metal Charpy Data Irradiated in the HSST Program
Lowe A.
Effects of Radiation on KIc Curves for High Copper Welds
Haggag F., Iskander S., McCabe D., Menke B., Nanstad R.
Improved Correlations for Predicting the Effects of Neutron Radiation on Linde 80 Submerged-Arc Weld Metals
Lowe A., Pegram J.
Fracture Toughness Shifts and Bounds for Irradiated Reactor Pressure Vessel Materials
Griesbach T., Server W.
Comparison of Experimental 41 J Shifts with the Predictions of German KTA 3203 and U.S. NRC Regulatory Guide 1.99
Ahlf J., Bellmann D.
The Nil-Ductility Temperature Shift Arising from Irradiation as Predicted Through the French Test Reactor Experiments
Dussarte D., Miannay D., Soulat P.
The Effects of Mechanical Stress Gradients on Irradiation-Induced Embrittlement of Pressure Vessel Steel
Ougouag A., Stubbins J., Williams J.
The Effect of Nickel on Irradiation Hardening of Pressure Vessel Steels
Lucas G., Odette G.
Fracture Resistance of Irradiated Stainless Steel Clad Vessels
McCabe D.
Tensile and Charpy Impact Behavior of an Irradiated Three-Wire Series-Arc Stainless Steel Cladding
Alexander D., Corwin W., Haggag F., Nanstad R.
Correlation of Cv and Drop-Weight Transition Temperature Increase Caused by Irradiation
Schmitt F.
Residual Tensile Properties at Low and High Strain Rates of AISI 316H Predamaged by Creep, Low Cycle Fatigue, and Irradiation to 2 dpa
Albertini C., Forlani M., Grande A., Iida K., Montagnani M., Pachera A.
Response of Ferritic/Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K
Asakura K., Hamada K., Kohyama A., Matsui H.
Serrated Flow in Irradiated and Partially Denitrided Mild Steel
Mahmood S., Murty K.
Effects of High Thermal and High Fast Fluences on the Mechanical Properties of Type 6061 Aluminum on the HFBR
Czajkowski C., Tichler P., Weeks J.
Charpy Impact Test Results of Ferritic Alloys Irradiated to 10 dpa at 55°C
Gelles D., Hu W.
Fracture Behavior of Ferritic Steels Irradiated at 50°C in the High-Flux Isotope Reactor (HFIR)
Huang F.
Evaluation of the Fracture Toughness of Irradiated Stainless Steel Using Short Rod Specimens
Clarke W., Ranganath S., White M.
Effect of Specimen Size on the Upper Shelf Energy of Ferritic Steels
Garner F., Hamilton M., Kumar A.
Evaluation of Irradiation Embrittlement by Instrumented Impact Testing
Anantharaman S., Chatterjee S., Sivaramakrishnan K., Viswanathan U.
Evaluation of Ring Tensile Test Results—A Semiempirical Approach
Anantharaman S., Balakrishnan K., Chatterjee S., Sivaramakrishnan K.
Irradiation Creep Behavior of the Fusion Heats of HT9 and Modified 9Cr-1 Mo Steels
Garner F., Puigh R.
Irradiation Creep in Austenitic Stainless Steels at 60 to 400°C with a Fusion Reactor Helium to dpa Ratio
Grossbeck M., Mansur L., Tanaka M.
Influence of Thermomechanical Treatment and Environmental History on Creep, Swelling, and Embrittlement of AISI 316 at 400°Cand 130 dpa
Garner F., Porter D., Wood E.
Swelling and In-Pile Creep Behavior of Some 15Cr15NiTi Stainless Steels in the Temperature Range 400 to 600°C
Bergmann H., Herschbach K., Schneider W.
The Cantilever Beam Method for Simulating Irradiation Creep and Growth
Hoelke C., Parsons J.
Effects of Neutron Irradiation to 98 dpa on the Swelling of Various Copper Alloys
Brager H., Garner F.
EURAC: A Concept for a European Accelerator Neutron Source
Bishop G., Kley W., Perlado J., Sinha A.
Analysis of Transmutation Nuclide Production in a Spallation Neutron Source
Sinha A., Srinivasan M.
Radiation Damage Calculations for Compound Materials
Greenwood L.
Neutron Spectra Calculations for Ex-Core Irradiation Experiments at the Buffalo Reactor
Hawthorne J., McGarry E., Prillinger G.
Consideration of Calculated and Experimental Neutron Dosimetry for Out-of-Core Metallurgy Irradiation Experiments at the Buffalo Reactor
Hawthorne J., McGarry E., Prillinger G., Rogers J.
Neutron-Induced Swelling of Commercial Alloys at Very High Exposures
Garner F., Gelles D.
Effect of Neutron Radiation on Mechanical Properties of Permanent Near Core Structures
Tavassoli A.
Influence of Swelling on Irradiated CW Titanium Modified 316 Embrittlement
Cauvin R., Fissolo A., Hugot J., Levy V.
The Influence of Creep Damage and Neutron Irradiation on the Tensile Properties of Type 304 Stainless Steel
Schaaf B.
Simulated Transient Behavior of HT9 Cladding
Cannon N., Hamilton M., Huang F.
The Swelling Behavior of Titanium-Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phénix
Blanchard P., Boulbin E., Dubuisson P., Hugot J., Maillard A., Pelletier M., Seran J., Touron H.
Irradiation Creep and Swelling of OX16H15M3B Steel and Its Modification 0X16H15M3BP Steel
Bibilashvili Y., Golovanov V., Golovnin I., Kalashnik G., Neustroev V., Povstyanko A., Romaneev V., Shamardin V.
Operational Behavior of FBR Mixed Oxide Fuel Pins
Biermann W., Ehrlich K., Mühling G.
In Situ High Voltage Electron Microscopy Investigation of Catastrophic Swelling in Uranium Intermetallic Fuels
Allen C., Birtcher R., Hofman G., Rehn L.
The Effect of Crystal Structure Stability on Swelling in Intermetallic Uranium Compounds
Birtcher R., Hofman G., Rest J.
Author Index
Subject Index
Committee: E10
Paper ID: STP1046V2-EB
DOI: 10.1520/STP1046V2-EB
ISBN-EB: 978-0-8031-8887-7
 ASTM International is a member of CrossRef.
0-8031-1266-1
978-0-8031-1266-7
STP1046V2-EB
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