Effects of zinc additions on the stress corrosion crack growth rate of sensitized stainless steel, Alloy 600 and Alloy 182 weld metal in 288 C water
Creators
- 1. GE Corp. Research and Development, Schenectady, NY (United States)
Description
ZnO additions to boiling water reactor (BWR) water have been the focus of recent interest, primarily because of their beneficial influence in reducing buildup of radioactive species such as Co60 in the oxide film of structural components, e.g., stainless steel piping. The effect of ZnO additions on stress corrosion crack growth rates were studied using 1T CT fracture mechanics specimens of sensitized type 304 stainless steel, sensitized Alloy 600, and Alloy 182 weld metal exposed to ∼288 C water containing various levels of dissolved oxygen and impurities. Zn levels of 5 to 100 ppb Zn2+ were evaluated and found to reduce crack growth rates for all materials and in all water chemistries. Many Zn tests involved long term exposure and were performed at somewhat reduced corrosion potential (e.g., from ∼+200 to 0 -+50 mVshe); variations in corrosion potential from +200, to +50, to -50 mVshe clearly had an important effect. The benefit of Zn appeared to be most pronounced when the growth rate was decreased (e.g., by corrosion potential). This was consistent with the findings of mechanistic studies, which showed that Zn decreased the repassivation response at times >104 s, which is associated with low crack tip strain rates, i.e., low growth rates. Reduced corrosion potentials are also expected to directly effect Zn, since high (crack mouth) corrosion potentials inhibit the transport of Zn2+ into the crack. Zn also increased the fracture strain of the oxide on stainless steel, and may also reduce crack growth rates by increasing the pH in the crack. Similar benefits are expected for other structural materials, such as nonsensitized or irradiated stainless steel, carbon steel, low alloy steel, and other nickel alloys
Additional details
Publishing Information
- Publisher
- NACE International.
- Imprint Place
- Houston, TX (United States)
- Imprint Title
- Corrosion/95 conference papers
- Imprint Pagination
- 5788 p.
- Journal Page Range
- p. 16, Paper 409.
Conference
- Title
- National Association of Corrosion Engineers (NACE) international annual conference and corrosion show.
- Acronym
- Corrosion '95
- Dates
- 26-31 Mar 1995.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27004439
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; COBALT 60; CRACK PROPAGATION; EXPERIMENTAL DATA; FILLER METALS; INCONEL 600; NICKEL BASE ALLOYS; REACTOR MATERIALS; STAINLESS STEEL-304; STRESS CORROSION; WATER CHEMISTRY; ZINC OXIDES
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; AUSTENITIC STEELS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COBALT ISOTOPES; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INCONEL ALLOYS; INFORMATION; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NICKEL ALLOYS; NIMONIC; NUCLEI; NUMERICAL DATA; ODD-ODD NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; THERMAL REACTORS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES; ZINC COMPOUNDS
Optional Information
- Secondary number(s)
- CONF-950304--.