Mechanism of Lead-Induced Stress Corrosion Cracking of Nickel-Based Alloys in High-Temperature Water

Sakai, Takeshi; Nakagomi, N.; Kikuchi, Toshiro; Aoki, Kai; Nakayasu, F.; Yamakawa, Kōji

doi:10.5006/1.3284879

Cited by 11 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Several PbSCC mechanisms, such as liquid metal embrittlement [1], selective grain boundary oxidation [2] and hydrogen embrittlement [5], have been proposed, but none of them gives a completely interpretation to the PbSCC phenomena. In recent decades, experimental evidences revealed that the susceptibility of PbSCC is related to the instability of passive films [1,6,7]. With the formation of passive films, the crack growth rate is essentially determined by anodic dissolution rate of materials and film rupture rate [8].…”

Section: Introductionmentioning

confidence: 99%

Investigation of passive films on nickel Alloy 690 in lead-containing environments

Peng

Luo

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 99%

Investigation of passive films on nickel Alloy 690 in lead-containing environments

Peng

Luo

et al. 2008

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…Effect of lead on the anodic behavior of the Ni alloys A selective dissolution of Ni from alloy 600 and alloy 690 in an acidic water environment containing lead has been demonstrated [7][8][9]. Lead increases the critical current density and the passive current density of alloy 600 and 690 in a caustic water containing a lead compound at elevated temperature [10,11].…”

Section: Results Discussionmentioning

confidence: 99%

“…The effect of lead regarding an increase of the active peak of alloy 800 and alloy 690 TT in a caustic solution was also shown at 300 o C [11]. Likewise, anodic peaks of alloy 600, 690 and 800 were increased by the addition of PbCl 2 in an acidic solution [7,8]. Based on the Pourbaix diagram [12], Cr oxide and Ni oxide are unstable in an alkaline solution and an acidic solution respectively.…”

Section: Results Discussionmentioning

confidence: 99%

Electrochemical Interpretation of a Stress Corrosion Cracking of Thermally Treated Ni Base Alloys in a Lead Contaminated Water

Hwang

Lim

Kim

et al. 2007

SSP

View full text Add to dashboard Cite

Since the PbSCC(Lead stress corrosion cracking) of alloy 600 tubing materials was reported by Copson and Dean in 1965, the effect of lead on a corrosion film and cracking morphology have been continually debated. An electrochemical interaction of lead with the alloying elements of SG tubings was studied and the corrosion products were analyzed. It was found that lead enhanced the anodic dissolution of alloy 600 and alloy 690 in the electrochemical test. The lead preferentially dissolved the Cr from the corrosion film of alloy 600 and alloy 690 in alkaline water. The lead ion seemed to penetrate into the TG crack tip and react with the corrosion film. A selective Cr depletion was observed to weaken the stability of the passive film on the alloys. Whereas passivity of Ni became stable in lead containing solution, Cr and Fe passivity became unstable.

show abstract

“…Sakai observed that neither PbCl 2 nor PbO raised the corrosion potential of Ni-base alloys in an acidic environment [4]. Hence the role of Pb compound as a potential increasing agent remains controversial.…”

Section: Alloy 600 and Alloy 690mentioning

confidence: 99%

“…Some studies on the reaction of lead with alloy 600 and alloy 690 have been reported [2][3][4][5]. However, there is thus far little reported research concerning the effect of lead on each element.…”

Section: Introductionmentioning

confidence: 99%

Role of lead in electrochemical reaction of alloy 600, alloy 690, Ni, Cr, and Fe in water

Hwang

Kim

2003

Met. Mater. Int.

View full text Add to dashboard Cite

It has been reported that lead causes stress corrosion cracking (SCC) in the secondary side of steam generators (SG) in pressurized water reactors (PWR). The materials of SG tubings are alloy 600, alloy 690, or alloy 800, among which the main alloying elements are Ni, Cr, and Fe. The effect of lead on the electrochemical behaviors of alloy 600 and alloy 690 using an anodic polarization technique was evaluated. We also obtained polarization curves of pure Ni, Cr, and Fe in water containing lead. As the amount of lead in the solution increased, critical current densities and passive current densities of alloy 600 and alloy 690 increased, while the breakdown potential of the alloys decreased. Lead increased critical current density and the passive current of Cr in pH 4 and pH 10. The instability of passive film of steam generator tubings in water containing lead might arise from the instability of Cr passivity.

show abstract

Mechanism of Lead-Induced Stress Corrosion Cracking of Nickel-Based Alloys in High-Temperature Water

Cited by 11 publications

References 0 publications

Investigation of passive films on nickel Alloy 690 in lead-containing environments

Investigation of passive films on nickel Alloy 690 in lead-containing environments

Electrochemical Interpretation of a Stress Corrosion Cracking of Thermally Treated Ni Base Alloys in a Lead Contaminated Water

Role of lead in electrochemical reaction of alloy 600, alloy 690, Ni, Cr, and Fe in water

Contact Info

Product

Resources

About