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Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume) Steele LE Pages: 399       Published: 1993

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Table of Contents

Overview
Steele LE

Radiation Stability of WWER-440 Vessel Materials
Amayev AD, Kryukov AM, Levit VI, Sokolov MA

Management of Neutron Radiation Embrittlement: A View from the United States
Griesbach TJ, Server WL

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-440 Reactor Pressure Vessels
Brumovský M, á Páv T

Surveillance Data on Neutron Embrittlement of Modern Low-Sensitivity Steel
Najer M, Glumac B, Loose A, Remec I, Trandafir A

A Utility Perspective on Management of Reactor Pressure Vessel Embrittlement
Perrin JS

Utilization of Reactor Pressure Vessel Surveillance Data in Support of Aging Management
Mager TR

An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels
Pavinich WA, Griesbach TJ, Server WL

B&W Owners Group Master Integrated Reactor Vessel Surveillance Program
Fyfitch S, Gross LB, Lowe AL, Moore KE, Yoon KK

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 JC, 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
Kupa , Beo 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 QC

Influence of Specimen Orientation on the Upper Shelf Energy and Transition Temperature Shift of Reactor Pressure Vessel Steel Base Metal
Leitz C, Klausnitzer EN, 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 OM, Zvezdin YuI, Shamardin VK, Tulyakov GA

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

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 PE, Houssin B, Bocquet P, Bethmont M

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

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

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

Neutron Fluence Management to Optimize Pressure Vessel Lifetime
Lefebvre JC, Leroy P, Rieg C, Schaeffer H, Nimal JC, 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 EN, 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-D, Schützler H-P, Viehrig H-W

Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing
Amayev AD, Kryukov AM, Sokolov MA

Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovské Bohunice for Its Radiation Embrittlement Regeneration
Kupa , epek

Sensitivity Analysis of Thermal and Stress Fields in the Core Belt of a Pressurized Water Reactor
Glumac B, Najer M

Author Index


Subject Index


Committee: E10
Paper ID: STP1170-EB
DOI: 10.1520/STP1170-EB

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