Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels

Caitlin Huotilainen (Corresponding Author), Mykola Ivanchenko, Pål Efsing, Ulla Ehrnsten

Research output: Contribution to journalArticleScientificpeer-review

Abstract

In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials removed from the steam generator inlet and crossover elbows of the Ringhals 2 pressurized water reactor nuclear power plant unit after approximately 92kh of full operating time. The thermal aging of these materials was investigated using the double loop electrochemical potentiokinetic reactivation method, coupled with indentation hardness measurements and microstructural characterizations, to identify correlations between the electrochemical behavior and traditional methods of investigating thermal aging embrittlement effects in cast stainless steels. While this electrochemical method can be easily employed to quantify thermal aging effects in materials aged at higher temperatures (e.g. greater than 350∘C), this study highlights the difficulties encountered when electrochemically evaluating the aging of materials exposed to nuclear power plant operating conditions.
Original languageEnglish
Pages (from-to)34-40
Number of pages7
JournalJournal of Nuclear Materials
Volume520
DOIs
Publication statusPublished - Jul 2019
MoE publication typeA1 Journal article-refereed

Fingerprint

Thermal aging
Stainless Steel
casts
stainless steels
Stainless steel
Nuclear power plants
nuclear power plants
Aging of materials
Pressurized water reactors
Embrittlement
pressurized water reactors
Steam generators
Austenitic stainless steel
Indentation
embrittlement
austenitic stainless steels
boilers
indentation
Hardness
crossovers

Keywords

  • cast stainless steel
  • double loop electochemical potentiokinetic reactivation
  • G-phase
  • nanoindentation
  • spinodal decomposition
  • thermal aging

Cite this

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title = "Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels",
abstract = "In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials removed from the steam generator inlet and crossover elbows of the Ringhals 2 pressurized water reactor nuclear power plant unit after approximately 92kh of full operating time. The thermal aging of these materials was investigated using the double loop electrochemical potentiokinetic reactivation method, coupled with indentation hardness measurements and microstructural characterizations, to identify correlations between the electrochemical behavior and traditional methods of investigating thermal aging embrittlement effects in cast stainless steels. While this electrochemical method can be easily employed to quantify thermal aging effects in materials aged at higher temperatures (e.g. greater than 350∘C), this study highlights the difficulties encountered when electrochemically evaluating the aging of materials exposed to nuclear power plant operating conditions.",
keywords = "cast stainless steel, double loop electochemical potentiokinetic reactivation, G-phase, nanoindentation, spinodal decomposition, thermal aging",
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Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels. / Huotilainen, Caitlin (Corresponding Author); Ivanchenko, Mykola; Efsing, Pål; Ehrnsten, Ulla.

In: Journal of Nuclear Materials, Vol. 520, 07.2019, p. 34-40.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels

AU - Huotilainen, Caitlin

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AU - Efsing, Pål

AU - Ehrnsten, Ulla

PY - 2019/7

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AB - In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials removed from the steam generator inlet and crossover elbows of the Ringhals 2 pressurized water reactor nuclear power plant unit after approximately 92kh of full operating time. The thermal aging of these materials was investigated using the double loop electrochemical potentiokinetic reactivation method, coupled with indentation hardness measurements and microstructural characterizations, to identify correlations between the electrochemical behavior and traditional methods of investigating thermal aging embrittlement effects in cast stainless steels. While this electrochemical method can be easily employed to quantify thermal aging effects in materials aged at higher temperatures (e.g. greater than 350∘C), this study highlights the difficulties encountered when electrochemically evaluating the aging of materials exposed to nuclear power plant operating conditions.

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