Fatigue, degradation, and fracture 1990

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:5416426

Bamford, W H ^[1]; Becht, C IV ^[2]; Bhandari, S ^[3]; Gilman, J D ^[4]; James, L A ^[5]; Prager, M ^[6]

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1. Westinghouse Energy Systems (US)
2. Becht Engineering Co., Inc. (US)
3. Framatome (FR)
4. Electric Power Research Institute (US)
5. Westinghouse Bettis Laboratory (US)
6. Materials Properties Council (US)

This book contains papers presented at the 1990 Pressure Vessels and Piping Conference. It is organized under the following headings: Environmental fatigue crack growth; Fatigue analysis and fracture assessment; Fatigue and fracture of piping; Fatigue and fracture of vessels; Degradation of ferritic, austenitic, and duplex stainless alloys in nuclear service.

• OSTI ID: 5416426
• Report Number(s): CONF-900617--; ISBN: 0-7918-0506-7
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
ACCIDENTS
ALLOYS
BOILERS
CHEMISTRY
CONTAINERS
CORROSION FATIGUE
CORROSIVE EFFECTS
CRACK PROPAGATION
DOCUMENT TYPES
ENVIRONMENTAL EFFECTS
FATIGUE
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MATERIALS TESTING
MECHANICAL PROPERTIES
MEETINGS
PHYSICAL RADIATION EFFECTS
PROBABILISTIC ESTIMATION
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR VESSELS
RELIABILITY
SAFETY ANALYSIS
SERVICE LIFE
STEELS
TESTING
WATER CHEMISTRY