Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions

R. S. Daum; A. T. Motta; D. A. Koss; D. D. Macdonald

Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions

R. S. Daum, A. T. Motta, D. A. Koss, D. D. Macdonald

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

Abstract

Slow strain-rate tensile testing of Ni-based Alloys X-750 and 625 was performed in high-purity, deaerated water in order to determine whether hydrogen embrittlement occurs in these alloys at room temperature and 288°C. These tests were conducted at an initial strain-rate of 4.6×10^-7/sec under both 30 psig nitrogen (0 cc H₂/kg H₂O STP) and 40 psig hydrogen (60 cc H₂/kg H₂O STP), on Alloy X-750 in two heat-treatment conditions and on Alloy 625 in a solution annealed and aged condition. At room temperature in the hydrogenated environment, both alloys showed a pronounced susceptibility to hydrogen embrittlement. The presence of hydrogen reduced both the elongation to failure and the reduction in area at fracture by about 50%. Fractography indicated a transition from ductile, transgranular failure in the nitrogen environment to predominantly intergranular fracture under hydrogenated conditions. Fractography of the specimens tested at room temperature showed a transition in crack growth behavior from mixed mode slip band decohesion in nitrogen environments to Mode I intergranular fracture path in hydrogenated environments. In contrast, hydrogen had no discernible effect on the measured properties at 288°C under the slow strain-rate conditions imposed.

Original language	English (US)
Title of host publication	Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Editors	S. Bruemmer, P. Ford, G. Was, S. Breummer, P. Ford, G. Was
Pages	179-187
Number of pages	9
State	Published - Dec 1 1999
Event	Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States Duration: Aug 1 1999 → Aug 5 1999

Publication series

Name	Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Other

Other	Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Country/Territory	United States
City	New Portbeach, CA
Period	8/1/99 → 8/5/99

All Science Journal Classification (ASJC) codes

General Engineering

Cite this

Daum, R. S., Motta, A. T., Koss, D. A., & Macdonald, D. D. (1999). Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions. In S. Bruemmer, P. Ford, G. Was, S. Breummer, P. Ford, & G. Was (Eds.), Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - (pp. 179-187). (Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -).

Daum, R. S. ; Motta, A. T. ; Koss, D. A. et al. / Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions. Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -. editor / S. Bruemmer ; P. Ford ; G. Was ; S. Breummer ; P. Ford ; G. Was. 1999. pp. 179-187 (Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -).

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title = "Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions",

abstract = "Slow strain-rate tensile testing of Ni-based Alloys X-750 and 625 was performed in high-purity, deaerated water in order to determine whether hydrogen embrittlement occurs in these alloys at room temperature and 288°C. These tests were conducted at an initial strain-rate of 4.6×10-7/sec under both 30 psig nitrogen (0 cc H2/kg H2O STP) and 40 psig hydrogen (60 cc H2/kg H2O STP), on Alloy X-750 in two heat-treatment conditions and on Alloy 625 in a solution annealed and aged condition. At room temperature in the hydrogenated environment, both alloys showed a pronounced susceptibility to hydrogen embrittlement. The presence of hydrogen reduced both the elongation to failure and the reduction in area at fracture by about 50%. Fractography indicated a transition from ductile, transgranular failure in the nitrogen environment to predominantly intergranular fracture under hydrogenated conditions. Fractography of the specimens tested at room temperature showed a transition in crack growth behavior from mixed mode slip band decohesion in nitrogen environments to Mode I intergranular fracture path in hydrogenated environments. In contrast, hydrogen had no discernible effect on the measured properties at 288°C under the slow strain-rate conditions imposed.",

author = "Daum, {R. S.} and Motta, {A. T.} and Koss, {D. A.} and Macdonald, {D. D.}",

year = "1999",

month = dec,

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booktitle = "Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -",

note = "Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - ; Conference date: 01-08-1999 Through 05-08-1999",

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Daum, RS, Motta, AT, Koss, DA & Macdonald, DD 1999, Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions. in S Bruemmer, P Ford, G Was, S Breummer, P Ford & G Was (eds), Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -. Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -, pp. 179-187, Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -, New Portbeach, CA, United States, 8/1/99.

Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions. / Daum, R. S.; Motta, A. T.; Koss, D. A. et al.
Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -. ed. / S. Bruemmer; P. Ford; G. Was; S. Breummer; P. Ford; G. Was. 1999. p. 179-187 (Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -).

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

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N2 - Slow strain-rate tensile testing of Ni-based Alloys X-750 and 625 was performed in high-purity, deaerated water in order to determine whether hydrogen embrittlement occurs in these alloys at room temperature and 288°C. These tests were conducted at an initial strain-rate of 4.6×10-7/sec under both 30 psig nitrogen (0 cc H2/kg H2O STP) and 40 psig hydrogen (60 cc H2/kg H2O STP), on Alloy X-750 in two heat-treatment conditions and on Alloy 625 in a solution annealed and aged condition. At room temperature in the hydrogenated environment, both alloys showed a pronounced susceptibility to hydrogen embrittlement. The presence of hydrogen reduced both the elongation to failure and the reduction in area at fracture by about 50%. Fractography indicated a transition from ductile, transgranular failure in the nitrogen environment to predominantly intergranular fracture under hydrogenated conditions. Fractography of the specimens tested at room temperature showed a transition in crack growth behavior from mixed mode slip band decohesion in nitrogen environments to Mode I intergranular fracture path in hydrogenated environments. In contrast, hydrogen had no discernible effect on the measured properties at 288°C under the slow strain-rate conditions imposed.

AB - Slow strain-rate tensile testing of Ni-based Alloys X-750 and 625 was performed in high-purity, deaerated water in order to determine whether hydrogen embrittlement occurs in these alloys at room temperature and 288°C. These tests were conducted at an initial strain-rate of 4.6×10-7/sec under both 30 psig nitrogen (0 cc H2/kg H2O STP) and 40 psig hydrogen (60 cc H2/kg H2O STP), on Alloy X-750 in two heat-treatment conditions and on Alloy 625 in a solution annealed and aged condition. At room temperature in the hydrogenated environment, both alloys showed a pronounced susceptibility to hydrogen embrittlement. The presence of hydrogen reduced both the elongation to failure and the reduction in area at fracture by about 50%. Fractography indicated a transition from ductile, transgranular failure in the nitrogen environment to predominantly intergranular fracture under hydrogenated conditions. Fractography of the specimens tested at room temperature showed a transition in crack growth behavior from mixed mode slip band decohesion in nitrogen environments to Mode I intergranular fracture path in hydrogenated environments. In contrast, hydrogen had no discernible effect on the measured properties at 288°C under the slow strain-rate conditions imposed.

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Daum RS, Motta AT, Koss DA, Macdonald DD. Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions. In Bruemmer S, Ford P, Was G, Breummer S, Ford P, Was G, editors, Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -. 1999. p. 179-187. (Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -).

Hydrogen-assisted failure of Alloys X-750 and 625 under low strain-rate conditions

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