Stress corrosion cracking of reactor pressure vessel steel in 288 C water: The effect of oxygen, electrochemical potential, and steel composition

Book · Sat Dec 31 04:00:00 EST 1994

OSTI ID:70090

Magdowski, R; Kraus, A; Speidel, M O ^[1]

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1. Swiss Federal Inst. of Technology, Zurich (Switzerland). Inst. of Metallurgy

A new set of fracture mechanics stress corrosion crack growth rate data is presented for transgranular cracking of reactor pressure steels in high temperature water. The essential observations are as follows. Fast stress corrosion crack growth rates between 10{sup {minus}9} and 10{sup {minus}8} m/s may be observed down to 400 ppb dissolved oxygen at water conductivities of 1.0 {mu}s/cm in refreshed autoclaves. Stress corrosion crack growth could not be observed below minus 270 mV on the hydrogen scale. Low and medium sulfur contents in the steels have no measurable influence on the stress corrosion crack growth rates in 288 C water with a conductivity of 1.0 {mu}S/cm.

• OSTI ID: 70090
• Report Number(s): CONF-940222--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CHEMICAL COMPOSITION
CRACK PROPAGATION
EXPERIMENTAL DATA
MECHANICAL PROPERTIES
PRESSURE VESSELS
REACTOR MATERIALS
STEEL-ASTM-A508
STEEL-ASTM-A533-B
STRESS CORROSION
SULFUR CONTENT
WATER CHEMISTRY
WATER COOLED REACTORS