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SEDL / STP / STP725-EB
Extensive information on current research results dealing with the effects of radiation on light-water-reactor pressure vessels, fast breeder reactor core materials, material for first-walls in fusion systems, and solid radioactive waste.
Table of Contents
Introduction
Kramer D.
Summary
Brager H., Perrin J.
Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels
Pachur D.
Radiation Embrittlement of a PWR Vessel Steel: Effects of Impurities and Nickel Content
Flavier C., Gros D., Guionnet C., Lefort A., Perdreau R., Robin Y.
Correlation Between Microhardness, Tensile Properties, and Notch Ductility of Irradiated Ferritic Steels
Holland J., Mancuso J., Shogan R., Spitznagel J.
Irradiation Surveillance Program as Applied in Switzerland
Njo D., Varga T.
Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits
Hawthorne J., Loss F., Watson H.
J-R Curve Characterization of A533-B Weld Metal with Irradiation and Postirradiation Annealing
Gray R., Hawthorne J., Loss F., Menke B., Watson H.
Influence of Neutron Irradiation on Mechanical Properties of Steels Under Impulsive Loading
Bílek Z., Buchar J.
Fatigue Crack Growth Rates of Irradiated Pressure Vessel Steels in Simulated Nuclear Coolant Environment
Cullen W., Taylor R., Torronen K., Watson H.
Significance of Radiation Effects in Solid Radioactive Waste
McDonell W., Permar P.
An Internally Consistent Model for Radiation-Induced Void Swelling
Liu Y., Nichols F.
Radiation-Enhanced Diffusion in Face-Centered Cubic Materials
Schüle W.
Positron Lifetime Studies of Electron-Irradiated Copper
Byrne J., Hadnagy T., Miller G.
Simulation of Short-Term Annealing of Displacement Cascades in Face-Centered Cubic Metals
Doran D., Heinisch H., Schwartz D.
High-Density Equation of State for Helium and Its Application to Bubbles in Solids
Wolfer W.
Applications of the Theory of Cavity Growth to Dual-Ion Swelling Experiments
Hayns M., Mansur L.
Ductility Loss of Ion-Irradiated Zircaloy-2 in Iodine Environment
Kamei H., Koizumi K., Shimada M., Terasawa M., Yamamoto S.
Radiation Hardening in Neutron-Irradiated Molybdenum and Its Alloys
Fukai K., Fukaya K., Shiraishi K., Tanaka M.
Fracture Resistance of HT-9 After Irradiation at Elevated Temperature
Hawthorne J., Provenzano V., Smidt F.
Tensile, Creep, and Fatigue Properties of Low-Fluence Neutron-Irradiated Welded Joints DIN 1.4948
de Vries M., van der Schaaf B.
Mechanical and Physical Properties of Irradiated Type 348 Stainless Steel
Beeston J.
Tensile Properties of Neutron-Irradiated Nimonic PE16
Bajaj R., Bleiberg M., DeFlitch C., Fish R., Paxton M., Shogan R.
Effects of Neutron Irradiation on Fatigue and Creep-Fatigue Crack Propagation in Type 316 Stainless Steel at 649°C
Michel D., Smith H.
State Variable Description of 316 Stainless Steel Postirradiation Mechanical Properties
Wire G.
A Microstructural Interpretation of the Fluence and Temperature Dependence of the Mechanical Properties of Irradiated AISI 316
Brager H., Fish R., Garner F., Johnson G.
Coarse Slip Processes and Crack Propagation in Irradiated Stainless Steel
Horton J., Jesser W.
Dynamic Mechanical Properties of AISI 304L Irradiated to 2.2 dpa
Albertini C., Del Grande A., Montagnani M.
Postirradiation Cladding Strength Under Biaxial Loading with an Increasing Temperature Ramp
Duncan D., Hunter C.
Microstructural Development in Dual-Ion-Bombarded 316 Stainless Steel
Choyke W., Doyle N., McGruer J., Spitznagel J., Townsend J., Wood S.
Microchemical Evolution of Neutron-Irradiated Stainless Steel
Brager H., Garner F.
Comparison of High-Fluence Swelling Behavior of Austenitic Stainless Steels
Boltax A., Weiner R.
Response to Annealing and Reirradiation of AISI 304L Stainless Steel Following Initial High-Dose Neutron Irradiation in EBR-II
McVay G., Porter D., Walters L.
Point-Defect Clustering in the Presence of Mobile Helium and Immobile Traps
Hall B.
Effects of Dose Rate on the Precipitate Distribution in an Ion-Irradiated Nickel-Aluminum Alloy
Malmberg P., Smidt F., Sprague J., Westmoreland J.
Swelling in Reactor-Conditioned Nickel-Ion Irradiated Nimonic PE16
Bajaj R., Bleiberg M., Chickering R., Diamond S.
Gamma Prime Coarsening and Redistribution in Nimonic PE16
Gelles D.
Effect of Material Variables on the Irradiation Performance of Boron Carbide
Basmajian J., Hollenberg G.
A Microstructural Explanation for the Low Swelling of Ferritic Steels
Bullough R., Little E., Wood M.
Irradiation-Induced Precipitation in Binary Palladium-Refractory Metal Alloys
Ardell A., Weaver L.
Void Swelling in Molybdenum Alloys In Situ Observed by a High-Voltage Electron Microscope
Igata N., Kohyama A., Nomura S.
A Study of Radiation Damage Produced in Thinned Specimens of 316 Stainless Steel by Energetic Helium Ions
Horton L., Jesser W.
Helium Bubble Growth in Vanadium
Goodhew P., Tyler S.
Irradiated Materials Measurement Technology
Chin B., Gilbert E.
Stress-Enhanced Swelling of Metals During Irradiation
Garner F., Gilbert E., Porter D.
Effect of Temperature Changes on Swelling and Creep of AISI 316
Foster J., Garner F., Gelles D., Gilbert E.
Reduction of Irradiation-Induced Creep and Swelling in AISI 316 by Compositional Modifications
Bates J., Gilbert E., Powell R.
Frank Loop Formation in Irradiated Metals in Response to Applied and Internal Stresses
Brager H., Garner F., Gelles D.
Index
Committee: E10
Paper ID: STP725-EB
DOI: 10.1520/STP725-EB
ISBN-EB: 978-0-8031-4794-2
 ASTM International is a member of CrossRef.
0-8031-0755-2
978-0-8031-0755-7
STP725-EB
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