Stress corrosion cracking susceptibility of irradiated Type 304 stainless steels

Conference · Sat Aug 01 04:00:00 EDT 1992

OSTI ID:6999924

Chung, H M; Ruther, W E; Sanecki, J E; Kassner, T F

Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control blade sheath after irradiation up to 2.5 [times] 10[sup 2l] n[center dot]cm[sup [minus]2] (E > l MeV) in boiling water reactors (BWRs). The susceptibility of the HP absorber tubes to intergranular stress corrosion cracking (IGSCC) was higher than that of the CP absorber tubes or the CP control blade sheath. IGSCC susceptibilities of the BWR components could not be correlated to segregation impurities on grain boundaries. However for comparable fluence levels, Cr on grain-boundaries.

• Research Organization: Argonne National Lab., IL (United States). Materials and Components Technology Div.
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6999924
• Report Number(s): ANL/MCT/CP-74743; CONF-9206282--2; ON: DE93003005
• 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
36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
AUSTENITIC STEELS
BARYONS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTROL ELEMENTS
CORROSION
CORROSION RESISTANT ALLOYS
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FAST NEUTRONS
FERMIONS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NEUTRON ABSORBERS
NEUTRONS
NICKEL ALLOYS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRESS CORROSION
TEMPERATURE RANGE
TEMPERATURE RANGE 0400-1000 K
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS