Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures

Qunjia Peng; Tetsuo Shoji; Juan Hou; Yoichi Takeda; Toshio Yonezawa

Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures

Qunjia Peng, Tetsuo Shoji, Juan Hou, Yoichi Takeda, Toshio Yonezawa

ENG - Fracture and Reliability Research Institute

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

2 Citations (Scopus)

Abstract

Environmentally assisted crack (EAC) growth in thermally treated Alloy 690 (Alloy 690TT) cold worked one-dimensionally to the thickness reduction of 25% was investigated by crack growth rate testing in the primary water at low and high temperatures. In water at 50°C and a dissolved hydrogen (DH) of 2.7-2.9 ppm, the test results suggest that the crack growth rate is lower than 2.2×10^-9 mm/s at a stress intensity factor of 35 MPa√m. Stress corrosion cracking (SCC) growth with a rate of <1×10 ^-11 m/s was observed in the alloy in water at temperatures of 320°C and 340°C. Over a DH range of 0.37-2.6 ppm, the SCC growth in Alloy 690TT has a similar DH dependence as that in Alloy 600 and its weld metals. The magnitude of the DH dependence, however, is much smaller for Alloy 690TT. In water deaerated by N₂ without DH, an extremely low SCC growth rate was observed. Increasing DH in water from 0 ppm to 0.38 ppm caused an active SCC growth, suggesting that hydrogen could promote SCC growth when increasing DH from a very low level. Results of the current work confirmed a general high resistance of 25% cold worked Alloy 690TT to EAC growth in the primary water at both low and high temperatures under moderate stress intensity factors.

Original language	English
Title of host publication	15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Publisher	John Wiley and Sons Inc.
Pages	139-148
Number of pages	10
ISBN (Print)	9781622761944
Publication status	Published - 2011
Event	15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States Duration: 2011 Aug 7 → 2011 Aug 11

Publication series

Name	15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume	1

Conference

Conference	15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Country/Territory	United States
City	Colorado Springs, CO
Period	11/8/7 → 11/8/11

Keywords

Alloy 690TT
Cold working
Dissolved hydrogen
Environmentally assisted cracking
Primary water

Cite this

Peng, Q., Shoji, T., Hou, J., Takeda, Y., & Yonezawa, T. (2011). Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures. In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 (pp. 139-148). (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011; Vol. 1). John Wiley and Sons Inc..

Peng, Qunjia ; Shoji, Tetsuo ; Hou, Juan et al. / Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011. John Wiley and Sons Inc., 2011. pp. 139-148 (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011).

@inproceedings{1649de41f7e24f1b8bf2c7793251074e,

title = "Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures",

abstract = "Environmentally assisted crack (EAC) growth in thermally treated Alloy 690 (Alloy 690TT) cold worked one-dimensionally to the thickness reduction of 25% was investigated by crack growth rate testing in the primary water at low and high temperatures. In water at 50°C and a dissolved hydrogen (DH) of 2.7-2.9 ppm, the test results suggest that the crack growth rate is lower than 2.2×10-9 mm/s at a stress intensity factor of 35 MPa√m. Stress corrosion cracking (SCC) growth with a rate of <1×10 -11 m/s was observed in the alloy in water at temperatures of 320°C and 340°C. Over a DH range of 0.37-2.6 ppm, the SCC growth in Alloy 690TT has a similar DH dependence as that in Alloy 600 and its weld metals. The magnitude of the DH dependence, however, is much smaller for Alloy 690TT. In water deaerated by N2 without DH, an extremely low SCC growth rate was observed. Increasing DH in water from 0 ppm to 0.38 ppm caused an active SCC growth, suggesting that hydrogen could promote SCC growth when increasing DH from a very low level. Results of the current work confirmed a general high resistance of 25% cold worked Alloy 690TT to EAC growth in the primary water at both low and high temperatures under moderate stress intensity factors.",

keywords = "Alloy 690TT, Cold working, Dissolved hydrogen, Environmentally assisted cracking, Primary water",

author = "Qunjia Peng and Tetsuo Shoji and Juan Hou and Yoichi Takeda and Toshio Yonezawa",

year = "2011",

language = "English",

isbn = "9781622761944",

series = "15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011",

publisher = "John Wiley and Sons Inc.",

pages = "139--148",

booktitle = "15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011",

address = "United States",

note = "15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 ; Conference date: 07-08-2011 Through 11-08-2011",

}

Peng, Q, Shoji, T, Hou, J, Takeda, Y & Yonezawa, T 2011, Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures. in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011, vol. 1, John Wiley and Sons Inc., pp. 139-148, 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011, Colorado Springs, CO, United States, 11/8/7.

Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures. / Peng, Qunjia; Shoji, Tetsuo; Hou, Juan et al.
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011. John Wiley and Sons Inc., 2011. p. 139-148 (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures

AU - Peng, Qunjia

AU - Shoji, Tetsuo

AU - Hou, Juan

AU - Takeda, Yoichi

AU - Yonezawa, Toshio

PY - 2011

Y1 - 2011

N2 - Environmentally assisted crack (EAC) growth in thermally treated Alloy 690 (Alloy 690TT) cold worked one-dimensionally to the thickness reduction of 25% was investigated by crack growth rate testing in the primary water at low and high temperatures. In water at 50°C and a dissolved hydrogen (DH) of 2.7-2.9 ppm, the test results suggest that the crack growth rate is lower than 2.2×10-9 mm/s at a stress intensity factor of 35 MPa√m. Stress corrosion cracking (SCC) growth with a rate of <1×10 -11 m/s was observed in the alloy in water at temperatures of 320°C and 340°C. Over a DH range of 0.37-2.6 ppm, the SCC growth in Alloy 690TT has a similar DH dependence as that in Alloy 600 and its weld metals. The magnitude of the DH dependence, however, is much smaller for Alloy 690TT. In water deaerated by N2 without DH, an extremely low SCC growth rate was observed. Increasing DH in water from 0 ppm to 0.38 ppm caused an active SCC growth, suggesting that hydrogen could promote SCC growth when increasing DH from a very low level. Results of the current work confirmed a general high resistance of 25% cold worked Alloy 690TT to EAC growth in the primary water at both low and high temperatures under moderate stress intensity factors.

AB - Environmentally assisted crack (EAC) growth in thermally treated Alloy 690 (Alloy 690TT) cold worked one-dimensionally to the thickness reduction of 25% was investigated by crack growth rate testing in the primary water at low and high temperatures. In water at 50°C and a dissolved hydrogen (DH) of 2.7-2.9 ppm, the test results suggest that the crack growth rate is lower than 2.2×10-9 mm/s at a stress intensity factor of 35 MPa√m. Stress corrosion cracking (SCC) growth with a rate of <1×10 -11 m/s was observed in the alloy in water at temperatures of 320°C and 340°C. Over a DH range of 0.37-2.6 ppm, the SCC growth in Alloy 690TT has a similar DH dependence as that in Alloy 600 and its weld metals. The magnitude of the DH dependence, however, is much smaller for Alloy 690TT. In water deaerated by N2 without DH, an extremely low SCC growth rate was observed. Increasing DH in water from 0 ppm to 0.38 ppm caused an active SCC growth, suggesting that hydrogen could promote SCC growth when increasing DH from a very low level. Results of the current work confirmed a general high resistance of 25% cold worked Alloy 690TT to EAC growth in the primary water at both low and high temperatures under moderate stress intensity factors.

KW - Alloy 690TT

KW - Cold working

KW - Dissolved hydrogen

KW - Environmentally assisted cracking

KW - Primary water

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M3 - Conference contribution

AN - SCOPUS:84867586403

SN - 9781622761944

T3 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011

SP - 139

EP - 148

BT - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011

PB - John Wiley and Sons Inc.

T2 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011

Y2 - 7 August 2011 through 11 August 2011

ER -

Peng Q, Shoji T, Hou J, Takeda Y, Yonezawa T. Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures. In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011. John Wiley and Sons Inc. 2011. p. 139-148. (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011).

Environmentally assisted crack growth in cold worked alloy 690TT in primary water at low and high temperatures

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