Investigation of intergranular stress corrosion cracking in the fuel pool at Three Mile Island Unit 1

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:6224081

Czajkowski, C J

An intergranular stress corrosion cracking failure of 304 stainless steel pipe in 2000 ppM B as H/sub 3/BO/sub 3/ + H/sub 2/O at 100/sup 0/C has been investigated. Constant extension rate testing has produced an intergranular type failure in material in air. Chemical analysis was performed on both the base metal and weld material, in addition to fractography, EPR testing and optical microscopy in discerning the mode of failure. Various effects of Cl/sup -/, O/sub 2/, and MnS are discussed. The results have indicated that the cause of failure was the severe sensitization coupled with probable contamination by S and possibly by Cl ions.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6224081
• Report Number(s): BNL-NUREG-37614; CONF-851203-2; ON: TI86006873
• Resource Relation: Conference: International conference and exhibition on fatigue, corrosion cracking, fracture mechanic and failure analysis, Salt Lake City, UT, USA, 2 Dec 1985
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
STAINLESS STEEL-304
STRESS CORROSION
THREE MILE ISLAND-1 REACTOR
FUEL POOLS
BORATES
CRACKS
PIPES
ALLOYS
BORON COMPOUNDS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
ENRICHED URANIUM REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NICKEL ALLOYS
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STAINLESS STEELS
STEELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled