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SEDL / STP / STP909-EB
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STP909
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume)
Steele LE
Pages: 297
Published: 1986
Other books in this series
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STP 909 has sixteen peer-reviewed papers divided into four sections that reflect changes in the nuclear power industry occurring since 1981, including escalating capital requirements and a growing worldwide dependence on nuclear power for electricity production. The four sections of this book are: • Overview of National Programs
• Surveillance and Other Radiation Embrittlement Studies
• Pressure Vessel Integrity and Regulatory Considerations
• and Mechanisms of Irradiation Embrittlement.
Table of Contents
Introduction
Steele L.
Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels
Davies L., Ingham T.
Summary
Steele L.
Irradiation Effects in Reactor Pressure Vessel Steels: A Nuclear Regulatory Commission Perspective
Randall P., Serpan C.
Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components
Ahlf J., Bellmann D., Föhl J., Hebenbrock H., Schmitt F., Spalthoff W.
Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant
Ahlstrand R., Bärs B., Törrönen K., Valo M.
Effect of Irradiation on the Elasto-Plastic Toughness of Pressure Vessel Steels
Mundheri M., Petrequin P., Soulat P.
Prediction of Reference Transition Temperature Increase Due to Neutron Irradiation Exposure
Maricchiolo C., Milella P., Pini A.
Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program
Anantharaman S., Balakrishnan K., Chatterjee S., Roy P., Sivaramakrishnan K., Viswanathan U.
Static Fracture Criteria Evaluation Using Small Specimens
Gillemot F., Havas I., Szabó L.
Investigations and Measures to Guarantee the Safety of a Pressurized Water Reactor's Pressure Vessel Against Brittle Fracture
Kaun U., Koehring F.
Basis for Revision 2 of the U. S. Nuclear Regulatory Commission's Regulatory Guide 1.99
Randall P.
Reactor Pressure Vessel Structural Implications of Embrittlement to the Pressurized-Thermal-Shock Scenario
Föhl J., Iskander S., Sauter A.
Safety Standard KTA 3203: Monitoring Radiation Embrittlement of Reactor Pressure Vessels of Light-Water Reactors
Ernst K., Klausnitzer E., Leitz C.
Microanalytical Studies of Pressure Vessel Weld Materials
English C.
Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations
Lucas G., Odette G.
Annealing and Reirradiation Response of Irradiated Pressure Vessel Steels
Lott R., Mager T., Shogan R., Yanichko S.
Effect of Various Metallurgical Microstructures on the Response of the Nickel-Molybdenum-Chromium BH 70 Steel to Neutron Irradiation at 285°C
Vacek M.
Author Index
Subject Index
Committee: E10
Paper ID: STP909-EB
DOI: 10.1520/STP909-EB
ISBN-EB: 978-0-8031-4975-5
 ASTM International is a member of CrossRef.
0-8031-0473-1
978-0-8031-0473-0
STP909-EB
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