Fatigue, flaw evaluation and leak-before-break assessments 1994
Conference
·
OSTI ID:6912566
- eds.
The sessions in this volume deal with various aspects of fatigue and fracture in pressure boundary components such as piping, pressure vessels and steam generators. The sessions covered here are as follows: fatigue and fracture; constraint effects on fracture; dynamic analysis of cracked piping; load history effects on fracture; and considerations in pipe fracture analyses. Separate abstracts were prepared for 29 papers in this volume.
- OSTI ID:
- 6912566
- Report Number(s):
- CONF-940613--; ISBN: 0-7918-1353-3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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42 ENGINEERING
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ABSTRACTS
ALLOYS
BOILERS
CONTAINERS
CRACKS
DOCUMENT TYPES
DYNAMIC LOADS
FAILURES
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IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MATERIALS
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MEETINGS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
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STEAM GENERATORS
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THERMAL POWER PLANTS
VAPOR GENERATORS
210000* -- Nuclear Power Plants
22 GENERAL STUDIES OF NUCLEAR REACTORS
220000 -- Nuclear Reactor Technology
36 MATERIALS SCIENCE
360100 -- Metals & Alloys
42 ENGINEERING
420200 -- Engineering-- Facilities
Equipment
& Techniques
ABSTRACTS
ALLOYS
BOILERS
CONTAINERS
CRACKS
DOCUMENT TYPES
DYNAMIC LOADS
FAILURES
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MATERIALS
MECHANICS
MEETINGS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
REACTOR MATERIALS
STEAM GENERATORS
STEELS
THERMAL POWER PLANTS
VAPOR GENERATORS