...(1) K I = 4. P π . D 2 π . a ∑ i = 0 , i ≠ 1 4 ∑ j = 0 3 C i j ⋅ ( a D ) i ( a b ) j Abstract Stress corrosion cracking susceptibility of Zircaloy-4 (UNS R60804) wires was studied in 1M NaCl, 1M KBr and 1M...

...Abstract The stress corrosion cracking (SCC) susceptibility of h.c.p, metals was studied. The alloys used were: zirconium (UNS R60702), Zircaloy-4 (UNS R60804) and titanium (UNS R50400). The studies were performed in a 10 g/L iodine-methanol solution. SCC was observed in all the systems studied...

...Abstract The stress corrosion cracking (SCC) susceptibility of zirconium (UNS R60702) and one of its alloys, Zircaloy-4 (UNS R60804), was studied in 10 g/L iodine dissolved in various alcohols: methanol, ethanol, 1-propanol, 1-butanol, 1-pentanol and 1-octanol. SCC was observed in all the systems...

... expression for the pitting initiation potential found for other metals and alloys, ¹² according to Eq. (1) , Abstract Zircaloy-4 spent nuclear fuel cladding is considered as an additional metallic barrier for the containment of radionuclides in the proposed repository at Yucca Mountain...

...By the early 1970s, Zircaloy-4 became the standard fuel cladding material for pressurized water reactors (PWRs). Its performance with respect to waterside corrosion was quite satisfactory. However it was recognized that future PWRs were to be operated at higher coolant temperature with much higher...