| On the determination of the reference temperature T<sub>0</sub> of the Master-Curve method using subsized compact tension specimens
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| Present status of the FRACTESUS project: round robin on unirradiated materials
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| Probabilistic and deterministic investigation on single crack growth in dissimilar metal welds of a piping system
Mao, G., & Niffenegger, M. (2022). Probabilistic and deterministic investigation on single crack growth in dissimilar metal welds of a piping system. International Journal of Pressure Vessels and Piping, 195, 104566 (13 pp.). https://doi.org/10.1016/j.ijpvp.2021.104566 |
| State-of-the-art of WPS in RPV PTS analysis
Zarazovskii, M., Pistora, V., Lauerova, D., Obermeier, F., Mora, D., Dubyk, Y., … Shugailo, O. (2022). State-of-the-art of WPS in RPV PTS analysis. In Pressure vessels and piping conference. Proceedings of ASME 2022 pressure vessels and piping conference (PVP2022). Volume 1. Codes and standards (pp. PVP2022-83699 (11 pp.). https://doi.org/10.1115/PVP2022-83699 |
| Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels
Rao, G. S., Yagodzinskyy, Y., Que, Z., Spätig, P., & Seifert, H. P. (2021). Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels. Journal of Nuclear Materials, 556, 153161 (13 pp.). https://doi.org/10.1016/j.jnucmat.2021.153161 |
| Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Mora, D. F., Costa Garrido, O., Mukin, R., & Niffenegger, M. (2020). Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach. Engineering Fracture Mechanics, 238, 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258 |
| Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
Mora, D. F., Niffenegger, M., Qian, G., Jaros, M., & Niceno, B. (2019). Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM. Nuclear Engineering and Design, 353, 110237 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110237 |
| Degradation effects of hydrogen and high-temperature water environments on the fracture resistance of low-alloy RPV steels
Que, Z., Seifert, H. P., Spätig, P., Holzer, J., Zhang, A., Rao, G. S., & Ritter, S. (2019). Degradation effects of hydrogen and high-temperature water environments on the fracture resistance of low-alloy RPV steels. In Nineteenth international conference on environmental degradation of materials in nuclear power systems - water reactors (pp. 934-948). American Nuclear Society (ANS). |
| Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events
Chen, M., Yu, W., Qian, G., Shi, J., Cao, Y., & Yu, Y. (2018). Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events. Annals of Nuclear Energy, 116, 143-151. https://doi.org/10.1016/j.anucene.2018.01.032 |
| Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2018). Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel. Fatigue and Fracture of Engineering Materials and Structures, 41(7), 1559-1575. https://doi.org/10.1111/ffe.12796 |
| Effects of embedded cracks and residual stresses on the integrity of a reactor pressure vessel
Qian, G., González-Albuixech, V. F., & Niffenegger, M. (2018). Effects of embedded cracks and residual stresses on the integrity of a reactor pressure vessel. Engineering Failure Analysis, 90, 451-462. https://doi.org/10.1016/j.engfailanal.2018.04.009 |
| Presentation of DEFI-PROSAFE project: probabilistic methodology to assess margin in deterministic RPV integrity assessment and proposed benchmark
Tiete, R., Trewin, R., Blasset, S., Pistora, V., Posta, M., Niffenegger, M., & Qian, G. (2018). Presentation of DEFI-PROSAFE project: probabilistic methodology to assess margin in deterministic RPV integrity assessment and proposed benchmark. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 6A. ASME 2018 pressure vessels and piping conference. Proceedings papers. Materials and fabrication (pp. PVP2018-84615 (9 pp.). https://doi.org/10.1115/PVP2018-84615 |
| Fracture mechanics analyses of embedded cracks under PTS and effects of residual stresses
Qian, G., González-Albuixech, V. F., & Niffenegger, M. (2017). Fracture mechanics analyses of embedded cracks under PTS and effects of residual stresses. In Conference proceedings. Pressure vessels and piping conference: Vol. 6A-2017. Materials and fabrication (pp. PVP2017-66202 (7 pp.). https://doi.org/10.1115/PVP2017-66202 |
| Application of the French codes to the pressurized thermal shocks assessment
Chen, M., Qian, G., Shi, J., Wang, R., Yu, W., Lu, F., … Chen, Z. (2016). Application of the French codes to the pressurized thermal shocks assessment. Nuclear Engineering and Technology, 48(6), 1423-1432. https://doi.org/10.1016/j.net.2016.06.009 |
| Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects
González-Albuixech, V. F., Qian, G., Sharabi, M., Niffenegger, M., Niceno, B., & Lafferty, N. (2016). Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects. Engineering Fracture Mechanics, 162, 201-217. https://doi.org/10.1016/j.engfracmech.2016.05.010 |
| Analysis of a reactor pressure vessel subjected to pressurized thermal shocks
Niffenegger, M., Qian, G., Gonzalez-Albuixech, V. F., Sharabi, M., & Lafferty, N. (2016). Analysis of a reactor pressure vessel subjected to pressurized thermal shocks. The International Journal of Computational Methods and Experimental Measurements (CMEM), 4(3), 288-300. https://doi.org/10.2495/CMEM-V4-N3-288-300 |
| Deterministic and probabilistic PTS study for a reactor pressure vessel considering plume cooling effects
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2016). Deterministic and probabilistic PTS study for a reactor pressure vessel considering plume cooling effects. In Conference proceedings. Pressure vessels and piping conference: Vol. 6A-2016. Materials and fabrication (pp. PVP2016-63869 (12 pp.). https://doi.org/10.1115/PVP2016-63869 |
| Probabilistic pressurized thermal shock analysis for a reactor pressure vessel considering plume cooling effect
Qian, G., González-Albuixech, V. F., Niffenegger, M., & Sharabi, M. (2016). Probabilistic pressurized thermal shock analysis for a reactor pressure vessel considering plume cooling effect. Journal of Pressure Vessel Technology, 138(4), 041204 (8 pp.). https://doi.org/10.1115/1.4032197 |
| Investigation on constraint effect of a reactor pressure vessel subjected to pressurized thermal shocks
Qian, G., & Niffenegger, M. (2015). Investigation on constraint effect of a reactor pressure vessel subjected to pressurized thermal shocks. Journal of Pressure Vessel Technology, 137(1), 011204 (7 pp.). https://doi.org/10.1115/1.4028017 |
| Probabilistic pressurized thermal shocks analyses for a reactor pressure vessel
Qian, G., & Niffenegger, M. (2015). Probabilistic pressurized thermal shocks analyses for a reactor pressure vessel. Journal of Pressure Vessel Technology, 137(6), 061206 (7 pp.). https://doi.org/10.1115/1.4030299 |
