Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging

Teemu Sarikka; Roman Mouginot; Matias Ahonen; Sebastian Lindqvist; Ulla Ehrnstén; Pekka Nevasmaa; Hannu Hänninen

doi:10.1007/978-3-319-68454-3_58

Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging

Teemu Sarikka, Roman Mouginot, Matias Ahonen, Sebastian Lindqvist, Ulla Ehrnstén, Pekka Nevasmaa, Hannu Hänninen

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

1 Citation (Scopus)

Abstract

The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Editors	John H. Jackson, Denise Paraventi, Michael Wright
Publisher	Springer
Pages	763-777
Number of pages	15
Volume	2
ISBN (Electronic)	978-3-319-68454-3
ISBN (Print)	978-3-319-68453-6
DOIs	https://doi.org/10.1007/978-3-319-68454-3_58
Publication status	Published - 1 Jan 2018
MoE publication type	A4 Article in a conference publication
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: 13 Aug 2017 → 17 Aug 2017

Publication series

Series	Minerals, Metals and Materials Series
Number	Part F11
ISSN	2367-1181

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Abbreviated title	EDM 2017
Country	United States
City	Portland
Period	13/08/17 → 17/08/17

Keywords

Aging
Dissimilar metal weld
Microstructural characterization
Ni-base alloy

Access to Document

10.1007/978-3-319-68454-3_58

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Sarikka, T., Mouginot, R., Ahonen, M., Lindqvist, S., Ehrnstén, U., Nevasmaa, P., & Hänninen, H. (2018). Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (Vol. 2, pp. 763-777). Springer. Minerals, Metals and Materials Series, No. Part F11 https://doi.org/10.1007/978-3-319-68454-3_58

Sarikka, Teemu ; Mouginot, Roman ; Ahonen, Matias ; Lindqvist, Sebastian ; Ehrnstén, Ulla ; Nevasmaa, Pekka ; Hänninen, Hannu. / Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / John H. Jackson ; Denise Paraventi ; Michael Wright. Vol. 2 Springer, 2018. pp. 763-777 (Minerals, Metals and Materials Series; No. Part F11).

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abstract = "The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.",

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Sarikka, T, Mouginot, R, Ahonen, M, Lindqvist, S , Ehrnstén, U , Nevasmaa, P & Hänninen, H 2018, Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. in JH Jackson, D Paraventi & M Wright (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. vol. 2, Springer, Minerals, Metals and Materials Series, no. Part F11, pp. 763-777, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 13/08/17. https://doi.org/10.1007/978-3-319-68454-3_58

Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. / Sarikka, Teemu; Mouginot, Roman; Ahonen, Matias; Lindqvist, Sebastian ; Ehrnstén, Ulla ; Nevasmaa, Pekka; Hänninen, Hannu.

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / John H. Jackson; Denise Paraventi; Michael Wright. Vol. 2 Springer, 2018. p. 763-777 (Minerals, Metals and Materials Series; No. Part F11).

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

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AU - Mouginot, Roman

AU - Ahonen, Matias

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AU - Nevasmaa, Pekka

AU - Hänninen, Hannu

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AB - The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.

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Sarikka T, Mouginot R, Ahonen M, Lindqvist S , Ehrnstén U , Nevasmaa P et al. Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. In Jackson JH, Paraventi D, Wright M, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Vol. 2. Springer. 2018. p. 763-777. (Minerals, Metals and Materials Series; No. Part F11). https://doi.org/10.1007/978-3-319-68454-3_58