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STP1170 Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume) Steele LE Pages: 399 Published: 1993 Format: PDF (7.9M) Price: $103  [Download Now] Other books in this series

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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
Bros J., Ballesteros A., López A.

Analysis of the Surveillance Results at Paks Nuclear Power Plant
Oszvald F., Trampus P.

Surveillance of WWER-440Č Reactor Pressure Vessels
Brumovský M., áš Páv T.

Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel
Najžer M., Glumac B., Loose A., 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
Pavinich W., Griesbach T., 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
Van Duysen J., Bourgoin J., Moser P., Janot C.

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
Kupča &., Beňo P.

Fracture Properties of Irradiated A533B,Cl.1, A508,Cl.3, and 15Ch2NMFAA Reactor Pressure Vessel Steel
Havel R., Vacek M., Brumovský M.

Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content
Vacek M., Novosad P., Havel R.

Investigation on the Impact Strength and Toughness of A533 Grade B Composition Weld Metal Using Small Specimens
Varga T., Liu Q.

Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal
Leitz C., Klausnitzer E., Hofmann G.

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
Vishkarev O., Zvezdin Y., Shamardin V., Tulyakov G.

Radiation Effects on the Mechanical Properties of SA 508 Cl.3 Forging
Milella P., Pini A., Marschall C.

Irradiation Response of the IAEA CRP-3 Material FFA Measured by Fracture Toughness Specimens
Valo M., Wallin K., Törrönen K., Ahlstrand R.

Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program
Soulat P., Houssin B., Bocquet P., Bethmont M.

Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels
Munier A., Schaller R., Mercier O., Waeber W.

Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels
Soulat P., Miannay D., Horowitz H.

Influence of Neutron Irradiation on the Microstructure and Mechanical Properties of 15Kh2MFA Steel
Páv T., Kočík J., Keilová E.

Neutron Fluence Management to Optimize Pressure Vessel Lifetime
Lefebvre J., Leroy P., Rieg C., Schaeffer H., Nimal J., Lloret R.

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
Popp K., Bergmann U., Bergner F., Hampe E., Leonhardt W., 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
Kupča &., Čepček &.

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