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Interim technical report on BWR feedwater and control rod drive return line nozzle cracking

Technical Report ·
OSTI ID:7302793
The problems of nozzle cracking in BWR feedwater and control rod drive systems are discussed and the interim NRC staff position on minimizing and correcting these problems is presented.
Research Organization:
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
OSTI ID:
7302793
Report Number(s):
NUREG-0312
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACOUSTIC TESTING
BWR TYPE REACTORS
CONTROL ROD DRIVES
CRACKS
FATIGUE
FEEDWATER
HYDROGEN COMPOUNDS
MATERIALS TESTING
MECHANICAL PROPERTIES
NONDESTRUCTIVE TESTING
NOZZLES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
REPAIR
TESTING
ULTRASONIC TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS