Investigation and evaluation of cracking in austenitic stainless steel piping of boiling water reactor plants. Technical report
The report covers the investigations of a series of cracks that occurred in the austenitic stainless steel bypass pipes around the discharge valves in the main recirculation loops of six domestic boiling water reactor plants and in the core spray pipes of one boiling water reactor plant. The report describes the recent cracking occurrences as well as similar occurrences in boiling water reactors in the past. The report concludes that the cracks that occurred in six domestic boiling water reactor plant units were the result of intergranular stress corrosion cracking caused by the combination of high residual stresses, light sensitization of the heat affected zones of welds, and the oxygen level normally found in the coolant for this type of reactor. (GRA)
- Research Organization:
- Nuclear Regulatory Commission, Washington, D.C. (USA)
- OSTI ID:
- 7140470
- Report Number(s):
- PB-246645; NUREG-75/067
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACKS
IRON ALLOYS
IRON BASE ALLOYS
PIPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STAINLESS STEELS
STEELS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS