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SEDL / STP / STP1170-EB
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STP1170
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume)
Steele LE
Pages: 399
Published: 1993
Other books in this series
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31 peer-reviewed papers cover: • National Perspectives • Surveillance Programs and Their Results • Fracture Approaches • Applied Research • Fundamental Research • Amelioration of Effects.
Table of Contents
Overview
Steele L.
Radiation Stability of WWER-440 Vessel Materials
Amayev A., Kryukov A., Levit V., Sokolov M.
Management of Neutron Radiation Embrittlement: A View from the United States
Griesbach T., Server W.
Radiation Embrittlement of Spanish Nuclear Reactor Pressure Vessel Steels
Ballesteros A., Bros J., López A.
Analysis of the Surveillance Results at Paks Nuclear Power Plant
Oszvald F., Trampus P.
Surveillance of WWER-440Č Reactor Pressure Vessels
áš Páv T., Brumovský M.
Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel
Glumac B., Loose A., Najžer M., Remec I., Trandafir A.
A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement
Perrin J.
Utilization of Reactor Pressure Vessel Surveillance Data in Support of Aging Management
Mager T.
An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels
Griesbach T., Pavinich W., Server W.
B&W Owners Group Master Integrated Reactor Vessel Surveillance Program
Fyfitch S., Gross L., Lowe A., Moore K., Yoon K.
Study by Positron Annihilation of Neutron Damage in a Pressurized Water Reactor (PWR) Pressure Vessel Steel After a 13-Year Irradiation in the CHOOZ A Reactor Surveillance Program
Bourgoin J., Janot C., Moser P., Van Duysen J.
Surveillance Dosimetry of the French 900-MW Pressurized Water Reactors (PWRs): Results, Uncertainties, and Reactor Series Effects
Lloret R.
Analysis of the Results from the Surveillance Specimen Program for Reactor Pressure Vessels of Nuclear Power Plant W-2 in Jaslovské Bohunice
Beňo P., Kupča &.
Fracture Properties of Irradiated A533B,Cl.1, A508,Cl.3, and 15Ch2NMFAA Reactor Pressure Vessel Steel
Brumovský M., Havel R., Vacek M.
Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content
Havel R., Novosad P., Vacek M.
Investigation on the Impact Strength and Toughness of A533 Grade B Composition Weld Metal Using Small Specimens
Liu Q., Varga T.
Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal
Hofmann G., Klausnitzer E., Leitz C.
Mechanical and Nondestructive Testing of Irradiated Half Charpy Specimens
Gillemot F., Oszwald F., Pozsgay G.
Radiation Embrittlement of Soviet 1000-MW Pressurized Water Reactor Vessel Steel 15KH2NMFAA
Shamardin V., Tulyakov G., Vishkarev O., Zvezdin Y.
Radiation Effects on the Mechanical Properties of SA 508 Cl.3 Forging
Marschall C., Milella P., Pini A.
Irradiation Response of the IAEA CRP-3 Material FFA Measured by Fracture Toughness Specimens
Ahlstrand R., Törrönen K., Valo M., Wallin K.
Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program
Bethmont M., Bocquet P., Houssin B., Soulat P.
Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels
Mercier O., Munier A., Schaller R., Waeber W.
Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels
Horowitz H., Miannay D., Soulat P.
Influence of Neutron Irradiation on the Microstructure and Mechanical Properties of 15Kh2MFA Steel
Keilová E., Kočík J., Páv T.
Neutron Fluence Management to Optimize Pressure Vessel Lifetime
Lefebvre J., Leroy P., Lloret R., Nimal J., Rieg C., Schaeffer H.
Evaluation of the Recovery Annealing of the Reactor Pressure Vessel of NPP Nord (Greifswald) Units 1 and 2 by Means of Subsize Impact Specimens
Ahlstrand R., Klausnitzer E., Lange D., Leitz C., Pastor D., Valo M.
Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel
Bergmann U., Bergner F., Hampe E., Leonhardt W., Popp K., Schützler H., Viehrig H.
Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing
Amayev A., Kryukov A., Sokolov M.
Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovské Bohunice for Its Radiation Embrittlement Regeneration
Čepček &., Kupča &.
Sensitivity Analysis of Thermal and Stress Fields in the Core Belt of a Pressurized Water Reactor
Glumac B., Najžer M.
Author Index
Subject Index
Committee: E10
Paper ID: STP1170-EB
DOI: 10.1520/STP1170-EB
ISBN-EB: 978-0-8031-5228-1
 ASTM International is a member of CrossRef.
0-8031-1478-8
978-0-8031-1478-4
STP1170-EB
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