Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water

Seppo Tähtinen; Hannu Hänninen; Margareta Trolle

Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water

Seppo Tähtinen, Hannu Hänninen, Margareta Trolle

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

6 Citations (Scopus)

Abstract

The results of the failure analysis, material characterization and stress corrosion cracking (SCC) tests of cold bent, seamless austenitic stainless steel pipes removed from scram system 354 of Ringhals 1 BWR plant after 11 years operating time at 240 °C are presented. The material characterization and also the stress corrosion cracking susceptibility study of the cold bent pipes were performed for materials taken from different depths of the pipe wall thickness. Stress corrosion tests were carried out in simulated BWR water environments at 288°C with varying oxygen contents. The results indicated that highly cold worked material is susceptible to IGSCC without any marked sensitization under constant loading, while dynamic loading results in TGSCC.

Original language	English
Title of host publication	Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems
Subtitle of host publication	Water Reactors
Editors	Robert E. Gold, Edward P. Simonen
Place of Publication	Warrendale
Publisher	Minerals, Metals and Materials Society (TMS)
Pages	265-275
ISBN (Print)	978-0-87339-258-7
Publication status	Published - 1993
MoE publication type	A4 Article in a conference publication
Event	6th International symposium on Environmental Degradation in Nuclear Power Systems - San Diego, United States Duration: 1 Aug 1993 → 5 Aug 1993

Conference

Conference	6th International symposium on Environmental Degradation in Nuclear Power Systems
Country/Territory	United States
City	San Diego
Period	1/08/93 → 5/08/93

Cite this

Tähtinen, S., Hänninen, H., & Trolle, M. (1993). Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. In R. E. Gold, & E. P. Simonen (Eds.), Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors (pp. 265-275). Minerals, Metals and Materials Society (TMS).

Tähtinen, Seppo ; Hänninen, Hannu ; Trolle, Margareta. / Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. editor / Robert E. Gold ; Edward P. Simonen. Warrendale : Minerals, Metals and Materials Society (TMS), 1993. pp. 265-275

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title = "Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water",

abstract = "The results of the failure analysis, material characterization and stress corrosion cracking (SCC) tests of cold bent, seamless austenitic stainless steel pipes removed from scram system 354 of Ringhals 1 BWR plant after 11 years operating time at 240 °C are presented. The material characterization and also the stress corrosion cracking susceptibility study of the cold bent pipes were performed for materials taken from different depths of the pipe wall thickness. Stress corrosion tests were carried out in simulated BWR water environments at 288°C with varying oxygen contents. The results indicated that highly cold worked material is susceptible to IGSCC without any marked sensitization under constant loading, while dynamic loading results in TGSCC.",

author = "Seppo T{\"a}htinen and Hannu H{\"a}nninen and Margareta Trolle",

note = "HUO: YDINVOIMALAITOSTEN RAKENTEELLINEN TURVALLISUUS Project code: MET301831; 6th International symposium on Environmental Degradation in Nuclear Power Systems ; Conference date: 01-08-1993 Through 05-08-1993",

year = "1993",

language = "English",

isbn = "978-0-87339-258-7",

pages = "265--275",

editor = "Gold, {Robert E.} and Simonen, {Edward P.}",

booktitle = "Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems",

publisher = "Minerals, Metals and Materials Society (TMS)",

address = "United States",

}

Tähtinen, S, Hänninen, H & Trolle, M 1993, Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. in RE Gold & EP Simonen (eds), Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Minerals, Metals and Materials Society (TMS), Warrendale, pp. 265-275, 6th International symposium on Environmental Degradation in Nuclear Power Systems, San Diego, California, United States, 1/08/93.

Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. / Tähtinen, Seppo; Hänninen, Hannu; Trolle, Margareta.

Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. ed. / Robert E. Gold; Edward P. Simonen. Warrendale : Minerals, Metals and Materials Society (TMS), 1993. p. 265-275.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water

AU - Tähtinen, Seppo

AU - Hänninen, Hannu

AU - Trolle, Margareta

N1 - HUO: YDINVOIMALAITOSTEN RAKENTEELLINEN TURVALLISUUS Project code: MET301831

PY - 1993

Y1 - 1993

N2 - The results of the failure analysis, material characterization and stress corrosion cracking (SCC) tests of cold bent, seamless austenitic stainless steel pipes removed from scram system 354 of Ringhals 1 BWR plant after 11 years operating time at 240 °C are presented. The material characterization and also the stress corrosion cracking susceptibility study of the cold bent pipes were performed for materials taken from different depths of the pipe wall thickness. Stress corrosion tests were carried out in simulated BWR water environments at 288°C with varying oxygen contents. The results indicated that highly cold worked material is susceptible to IGSCC without any marked sensitization under constant loading, while dynamic loading results in TGSCC.

AB - The results of the failure analysis, material characterization and stress corrosion cracking (SCC) tests of cold bent, seamless austenitic stainless steel pipes removed from scram system 354 of Ringhals 1 BWR plant after 11 years operating time at 240 °C are presented. The material characterization and also the stress corrosion cracking susceptibility study of the cold bent pipes were performed for materials taken from different depths of the pipe wall thickness. Stress corrosion tests were carried out in simulated BWR water environments at 288°C with varying oxygen contents. The results indicated that highly cold worked material is susceptible to IGSCC without any marked sensitization under constant loading, while dynamic loading results in TGSCC.

M3 - Conference article in proceedings

SN - 978-0-87339-258-7

SP - 265

EP - 275

BT - Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems

A2 - Gold, Robert E.

A2 - Simonen, Edward P.

PB - Minerals, Metals and Materials Society (TMS)

CY - Warrendale

T2 - 6th International symposium on Environmental Degradation in Nuclear Power Systems

Y2 - 1 August 1993 through 5 August 1993

ER -

Tähtinen S, Hänninen H, Trolle M. Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. In Gold RE, Simonen EP, editors, Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Warrendale: Minerals, Metals and Materials Society (TMS). 1993. p. 265-275

Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water

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