Zaiqing Que

Research Scientist, BA2F04 Nuclear reactor materials

Phone+358401271984

Research output per year

If you made any changes in Pure these will be visible here soon.

Fingerprint

Dive into the research topics where Zaiqing Que is active. These topic labels come from the works of this person. Together they form a unique fingerprint.

5 Similar Profiles

Network

Recent external collaboration on country level. Dive into details by clicking on the dots.

1 Active
2 Finished

INCEFA-SCALE: INcreasing safety in NPPs by Covering gaps in Environmental Fatigue Assessment - focusing on gaps between laboratory data and component SCALE
Huotilainen, C., Seppänen, T., Que, Z., Ehrnstén, U. & Lydman, J.
1/10/20 → 30/09/25
Project: EU project
TAAN: Thermal Aging of Alloy 690 and a high Ni Alloy
Huotilainen, C., Que, Z. & Ehrnstén, U.
1/01/19 → 31/12/19
Project: Other
INCEFA-PLUS: Increasing safety in NPPs by Covering gaps in Environmental Fatigue Assessment
Huotilainen, C., Seppänen, T., Que, Z., Lydman, J. & Ehrnstén, U.
1/07/15 → 31/10/20
Project: EU project

9 Article
4 Conference article in proceedings
2 Report
1 Chapter or book article
3 More

Effect of thermal ageing at 400 °C on the microstructure of ferrite-austenite interface of nickel-base alloy narrow-gap dissimilar metal weld
Ahonen, M., Mouginot, R., Sarikka, T., Lindqvist, S., Que, Z., Ehrnstén, U., Virkkunen, I. & Hänninen, H., Mar 2020, In : Metals. 10, 3, 421.
Research output: Contribution to journal › Article › Scientific › peer-review

Open Access
Degradation Effects of Hydrogen and High-Temperature Water Environment on the Fracture Resistance of Low-Alloy RPV Steels
Que, Z., Seifert, H-P., Spätig, P., Zhang, A., Holzer, J., Rao, G. S. & Ritter, S., 2019, 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. cd-rom ed. American Nuclear Society (ANS), p. 934-948 15 p.
Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
2 Downloads (Pure)
Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments
Que, Z., Seifert, H. P., Spätig, P., Zhang, A., Holzer, J., Rao, G. S. & Ritter, S., 15 May 2019, In : Corrosion Science. 152, p. 172-189 18 p.
Research output: Contribution to journal › Article › Scientific › peer-review
4 Citations (Scopus)
Effect of high-temperature water environment on the fracture behaviour of low-alloy RPV steels
Que, Z., Seifert, H. P., Spätig, P., Sudhakar, R. G. & Ritter, S., 2019, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors. Springer, p. 1077-1099 23 p. (Minerals, Metals and Materials Series).
Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents
Que, Z., Seifert, H. P., Spätig, P., Holzer, J., Zhang, A., Rao, G. S. & Ritter, S., 1 Jul 2019, In : Corrosion Science. 154, p. 191-207 17 p.
Research output: Contribution to journal › Article › Scientific › peer-review
3 Citations (Scopus)