Abstract
Determination of the fracture toughness properties and thermal aging behavior of dissimilar metal weld (DMW) joints is of utmost importance for successful structural integrity and lifetime analyses. This paper presents results from fracture resistance (J-R), fracture toughness (T0) and Charpy-V impact toughness tests as well as fractography performed for an industrially manufactured narrow-gap DMW mock-up (SA508-Alloy 52-AISI 316L). Tests were performed on post-weld heat treated, 5000 h aged and 10,000 h aged material. The results show that this DMW is tough at the SA 508-Alloy 52 interface, which typically is the weakest zone of a DMW. The DMW joint maintains its high fracture resistance also after thermal aging. Crack propagates for a large part in the carbon-depleted zone (CDZ) of SA 508 but deflects occasionally to the Alloy 52 side due to small weld defects in µm scale. Ductile-to-brittle transition temperature determined from Charpy-V impact toughness tests increases due to thermal aging, but only to a minor extent. No significant change is observed for the T0 transition temperature due to aging.
| 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 | 733-747 |
| 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
| Name | Minerals, Metals and Materials Series |
|---|---|
| Number | Part F11 |
| ISSN (Print) | 2367-1181 |
| ISSN (Electronic) | 2367-1696 |
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 |
Fingerprint
Keywords
- Aging
- Dissimilar metal weld
- Microstructural characterization
- Ni-base alloy
Cite this
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Effect of thermal aging on fracture mechanical properties and crack propagation behavior of alloy 52 narrow-gap dissimilar metal weld. / Ahonen, Matias; Lindqvist, Sebastian; Sarikka, Teemu; Lydman, Jari; Mouginot, Roman; 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. 733-747 (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 - Effect of thermal aging on fracture mechanical properties and crack propagation behavior of alloy 52 narrow-gap dissimilar metal weld
AU - Ahonen, Matias
AU - Lindqvist, Sebastian
AU - Sarikka, Teemu
AU - Lydman, Jari
AU - Mouginot, Roman
AU - Ehrnstén, Ulla
AU - Nevasmaa, Pekka
AU - Hänninen, Hannu
PY - 2018/1/1
Y1 - 2018/1/1
N2 - Determination of the fracture toughness properties and thermal aging behavior of dissimilar metal weld (DMW) joints is of utmost importance for successful structural integrity and lifetime analyses. This paper presents results from fracture resistance (J-R), fracture toughness (T0) and Charpy-V impact toughness tests as well as fractography performed for an industrially manufactured narrow-gap DMW mock-up (SA508-Alloy 52-AISI 316L). Tests were performed on post-weld heat treated, 5000 h aged and 10,000 h aged material. The results show that this DMW is tough at the SA 508-Alloy 52 interface, which typically is the weakest zone of a DMW. The DMW joint maintains its high fracture resistance also after thermal aging. Crack propagates for a large part in the carbon-depleted zone (CDZ) of SA 508 but deflects occasionally to the Alloy 52 side due to small weld defects in µm scale. Ductile-to-brittle transition temperature determined from Charpy-V impact toughness tests increases due to thermal aging, but only to a minor extent. No significant change is observed for the T0 transition temperature due to aging.
AB - Determination of the fracture toughness properties and thermal aging behavior of dissimilar metal weld (DMW) joints is of utmost importance for successful structural integrity and lifetime analyses. This paper presents results from fracture resistance (J-R), fracture toughness (T0) and Charpy-V impact toughness tests as well as fractography performed for an industrially manufactured narrow-gap DMW mock-up (SA508-Alloy 52-AISI 316L). Tests were performed on post-weld heat treated, 5000 h aged and 10,000 h aged material. The results show that this DMW is tough at the SA 508-Alloy 52 interface, which typically is the weakest zone of a DMW. The DMW joint maintains its high fracture resistance also after thermal aging. Crack propagates for a large part in the carbon-depleted zone (CDZ) of SA 508 but deflects occasionally to the Alloy 52 side due to small weld defects in µm scale. Ductile-to-brittle transition temperature determined from Charpy-V impact toughness tests increases due to thermal aging, but only to a minor extent. No significant change is observed for the T0 transition temperature due to aging.
KW - Aging
KW - Dissimilar metal weld
KW - Microstructural characterization
KW - Ni-base alloy
UR - http://www.scopus.com/inward/record.url?scp=85042439584&partnerID=8YFLogxK
U2 - 10.1007/978-3-319-68454-3_56
DO - 10.1007/978-3-319-68454-3_56
M3 - Conference article in proceedings
SN - 978-3-319-68453-6
VL - 2
T3 - Minerals, Metals and Materials Series
SP - 733
EP - 747
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 -