An integrated approach for the evaluation of BWR vessel internal corrosion
- EPRI, Palo Alto, CA (United States)
Intergranular stress corrosion cracking (IGSCC) of boiling water reactor (BWR) piping has been studied extensively since 1975 when cracks were discovered in eight operating BWR plants. This type of cracking has been known to occur when sensitized stainless steel material near welds is loaded or strained in the presence of the water environment containing dissolved oxygen. The three ingredients or necessary conditions for IGSCC initiation are sensitized microstructure, tensile stress, and oxygenated high-temperature water. The BWR internals and vessel attachments were made using the same materials and fabrication methods as the BWR piping systems that have experienced severe IGSCC in the past. These major structural components are difficult to inspect because of access limitations and would be very expensive to repair or replace.
- OSTI ID:
- 6960055
- Report Number(s):
- CONF-931160--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 69; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Lifetime estimation of a BWR core shroud in terms of IGSCC
Corrosion evaluation of two processes for chemical decontamination of BWR structural materials
Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
C CODES
CHEMICAL REACTIONS
COMPUTER CODES
CONTAINERS
CORROSION
COST BENEFIT ANALYSIS
DECISION MAKING
ECONOMIC ANALYSIS
ECONOMICS
ENRICHED URANIUM REACTORS
INTERGRANULAR CORROSION
MICROSTRUCTURE
POWER REACTORS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTORS
STRESS CORROSION
SURVEILLANCE
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS