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SEDL / STP / STP1513-EB
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STP1513
Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle: 24th Volume
Busby Jeremy, Hanson Brady
Pages: 286
Published: 2010
Other books in this series
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Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover:
• Surveillance programs around the world
• Detailed characterization of irradiated microstructures
• Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels
• Modeling helium bubbles
• Finite-element modeling of fuel bundles
• And much more!
Table of Contents
International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
Nanstad R., Server W.
Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches
Gérard R., Lucon E., Scibetta M.
Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR
Gundermann A., Hein H., Keim E., Schnabel H., Seibert T.
Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials
Dohi K., Ishino S., Nishida K., Nomoto A., Soneda N.
Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview
Bolton C., Flewitt P., Moskovic R., Wootton M.
Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
Rindelhardt U., Schuhknecht J., Viehrig H., Weiss F.
Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux
Dohi K., Matsuzawa H., Nishida K., Nomoto A., Soneda N., Tomimatsu M.
Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels
Iwase A., Matsuzawa H., Nishiyama Y., Onizawa K., Yamaguchi M.
Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
Cho H., Kasada R., Kimura A., Lee J.
Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels
Ghoniem N., Nagasawa K., Sharafat S., Takahashi A.
Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor
Anandaraj V., Karthik V., Kasi Viswanathan K., Muralidharan N., Parameswaran P., Raj B., Saroja S., Venkiteswaran C., Venugopal V., Vijayalakshmi M.
Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350
Garner F., Gusev M., Maksimkin O., Osipov I., Silniagina N.
Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel
Kondo K., Miwa Y., Nishinoiri K., Tsukada T., Yamashita S.
Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals
Garner F., Gusev M., Maksimkin O., Toktogulova D.
Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments
Freire-Canosa J., Lampman T., Popescu A.
Author Index
Subject Index
Committee: E10
Paper ID: STP1513-EB
DOI: 10.1520/STP1513-EB
ISBN-EB: 978-0-8031-8417-6
 ASTM International is a member of CrossRef.
978-0-8031-3425-6
STP1513-EB
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