Fracture mechanics, creep and fatigue analysis
Conference
·
OSTI ID:5455733
- Becht Engineering Co., Inc., Liberty Corner, NJ (US)
- Framatome, Paris (FR)
- Northern Research Labs., Risley (GB)
This book covers the proceedings of the 1988 ASME Pressure Vessels and Piping Converence. Topics include: Fatigue crack growth analysis of a 45{sup 0} PWR - lateral; Fatigue crack growth on straight pipes under thermal shocks; and The treatment of residual stress in defect assessment of austenitic fast reactor structures.
- OSTI ID:
- 5455733
- Report Number(s):
- CONF-8806209--
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ABSTRACTS
ALLOYS
CONTAINERS
CRACK PROPAGATION
DOCUMENT TYPES
EPITHERMAL REACTORS
FAST REACTORS
FATIGUE
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MECHANICAL PROPERTIES
MECHANICS
MEETINGS
PIPES
POWER REACTORS
PRESSURE VESSELS
PROCEEDINGS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
STEELS
STRESS ANALYSIS
THERMAL FATIGUE
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ABSTRACTS
ALLOYS
CONTAINERS
CRACK PROPAGATION
DOCUMENT TYPES
EPITHERMAL REACTORS
FAST REACTORS
FATIGUE
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MECHANICAL PROPERTIES
MECHANICS
MEETINGS
PIPES
POWER REACTORS
PRESSURE VESSELS
PROCEEDINGS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
STEELS
STRESS ANALYSIS
THERMAL FATIGUE
WATER COOLED REACTORS
WATER MODERATED REACTORS