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:10.1007/978-3-030-04639-2_134

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

^*Corresponding author for this work

Aalto University

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

2 Citations (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
Subtitle of host publication	Water Reactors
Editors	John H. Jackson, Denise Paraventi, Michael Wright
Place of Publication	Cham
Publisher	Springer
Pages	1979-1993
ISBN (Electronic)	978-3-030-04639-2
ISBN (Print)	978-3-030-04638-5
DOIs	https://doi.org/10.1007/978-3-030-04639-2_134
Publication status	Published - 2 Apr 2019
MoE publication type	A4 Article in a conference publication
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: 18 Aug 2019 → 22 Aug 2019

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 2019
Country/Territory	United States
City	Boston
Period	18/08/19 → 22/08/19

Funding

This study, carried out in parallel with that presented by Ahonen et al. on mechanical behavior, has been made in collaboration between Aalto University School of Engineering and VTT Technical Research Centre of Finland Ltd within the Nickel-base Alloy Welding Forum (NIWEL)-research project funded by TEKES, Finnish (Teollisuuden Voima Oyj and Fortum Oyj) and Swedish (Vattenfall AB and OKG AB) energy industry. The authors wish to express their gratitude for the funding and participation to the project.

Keywords

Aging
Dissimilar metal weld
Microstructural characterization
Ni-base alloy

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1007/978-3-030-04639-2_134

Cite this

Sarikka, T., Mouginot, R., Ahonen, M., Lindqvist, S., Ehrnstén, U., Nevasmaa, P., & Hänninen, H. (2019). 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 (pp. 1979-1993). Springer. https://doi.org/10.1007/978-3-030-04639-2_134

Sarikka, Teemu ; Mouginot, Roman ; Ahonen, Matias et al. / 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. Cham : Springer, 2019. pp. 1979-1993 (Minerals, Metals and Materials Series; No. Part F11).

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title = "Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging",

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 2019, 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. Springer, Cham, Minerals, Metals and Materials Series, no. Part F11, pp. 1979-1993, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 18/08/19. https://doi.org/10.1007/978-3-030-04639-2_134

Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. / Sarikka, Teemu; Mouginot, Roman; Ahonen, Matias et al.
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. Cham: Springer, 2019. p. 1979-1993 (Minerals, Metals and Materials Series; No. Part F11).

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

TY - GEN

T1 - Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging

AU - Sarikka, Teemu

AU - Mouginot, Roman

AU - Ahonen, Matias

AU - Lindqvist, Sebastian

AU - Ehrnstén, Ulla

AU - Nevasmaa, Pekka

AU - Hänninen, Hannu

PY - 2019/4/2

Y1 - 2019/4/2

N2 - 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.

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.

KW - Aging

KW - Dissimilar metal weld

KW - Microstructural characterization

KW - Ni-base alloy

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BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems

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A2 - Paraventi, Denise

A2 - Wright, Michael

PB - Springer

CY - Cham

T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019

Y2 - 18 August 2019 through 22 August 2019

ER -

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. Cham: Springer. 2019. p. 1979-1993. (Minerals, Metals and Materials Series; No. Part F11). doi: 10.1007/978-3-030-04639-2_134

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

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