Abstract
| 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 |
| Publisher | Springer |
| Pages | 1077-1099 |
| Number of pages | 23 |
| ISBN (Electronic) | 978-3-030-04639-2 |
| ISBN (Print) | 978-3-030-04638-5 |
| DOIs | |
| Publication status | E-pub ahead of print - 7 Oct 2017 |
| 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 |
|---|---|
| ISSN | 2367-1181 |
Conference
| Conference | 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 |
|---|---|
| Country | United States |
| City | Boston |
| Period | 18/08/19 → 22/08/19 |
Fingerprint
Keywords
- Dynamic strain aging
- Environmental assisted cracking
- Fracture resistance reduction
- Hydrogen embrittlement
- Low alloy steel
Cite this
}
Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels. / Que, Z. (Corresponding author); Seifert, Hans Peter; Spätig, Philippe; Sudhakar, Rao G.; Ritter, Stefan.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Springer, 2017. p. 1077-1099 (Minerals, Metals and Materials Series).Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels
AU - Que, Z.
AU - Seifert, Hans Peter
AU - Spätig, Philippe
AU - Sudhakar, Rao G.
AU - Ritter, Stefan
PY - 2017/10/7
Y1 - 2017/10/7
N2 - The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.
AB - The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.
KW - Dynamic strain aging
KW - Environmental assisted cracking
KW - Fracture resistance reduction
KW - Hydrogen embrittlement
KW - Low alloy steel
UR - http://www.scopus.com/inward/record.url?scp=85064066141&partnerID=8YFLogxK
U2 - 10.1007/978-3-030-04639-2_68
DO - 10.1007/978-3-030-04639-2_68
M3 - Conference article in proceedings
AN - SCOPUS:85064066141
SN - 978-3-030-04638-5
T3 - Minerals, Metals and Materials Series
SP - 1077
EP - 1099
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems
PB - Springer
ER -