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 | |
| 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 |
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Keywords
- Aging
- Dissimilar metal weld
- Microstructural characterization
- Ni-base alloy
Cite this
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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
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 - 2018/1/1
Y1 - 2018/1/1
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
UR - http://www.scopus.com/inward/record.url?scp=85042447435&partnerID=8YFLogxK
U2 - 10.1007/978-3-319-68454-3_58
DO - 10.1007/978-3-319-68454-3_58
M3 - Conference article in proceedings
AN - SCOPUS:85042447435
SN - 978-3-319-68453-6
VL - 2
T3 - Minerals, Metals and Materials Series
SP - 763
EP - 777
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Jackson, John H.
A2 - Paraventi, Denise
A2 - Wright, Michael
PB - Springer
ER -