An integrated approach for the evaluation of BWR vessel internal corrosion

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6960055

Sun, B K.H.; Chexal, B; Pathania, R; Nelson, L; Gilman, J ^[1]

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1. 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--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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