Dr. SHEN Pei (申沛)

Research Output

  1. 2019
  2. Published

    Modified Embedded Atom Method Potential for Modeling the Thermodynamic Properties of High Thermal Conductivity Beryllium Oxide

    Wei, J., Zhou, W., Zhou, W., Li, S., Shen, P., Ren, S. & Hu, A. & 1 others, Zhou, W., 30 Apr 2019, In: ACS Omega. 4, 4, p. 6339-6346

    Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 13
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  3. Published

    First-principles investigation of water adsorption on FeCrAl (1 1 0) surfaces

    Wei, J., Li, S., Zhou, W., Shen, P., Ren, S., Hu, A. & Zhou, W., 28 Jan 2019, In: Applied Surface Science. 465, p. 259-266

    Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 9
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  4. 2018
  5. Published

    Corium behavior and steam explosion risks: A review of experiments

    Shen, P., Zhou, W., Cassiaut-Louis, N., Journeau, C., Piluso, P. & Liao, Y., Nov 2018, In: Annals of Nuclear Energy. 121, p. 162-176

    Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 30
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  6. Published

    Numerical simulation of corium jet breakup during fuel-coolant interaction based on the ALISA test performed at KROTOS test facility

    Shen, P. & Zhou, W., Jul 2018, Proceedings of the 26th International Conference on Nuclear Engineering (ICONE26). American Society of Mechanical Engineers (ASME), Vol. 8 (Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance). V008T09A028. (International Conference on Nuclear Engineering; vol. 2018, no. ICONE26-81818).

    Research output: Chapters, Conference Papers, Creative and Literary WorksRGC 32 - Refereed conference paper (with host publication)peer-review

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  7. 2017
  8. Published

    In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches

    Shen, P. & Zhou, W., Jul 2017, Proceedings of the 2017 25th International Conference on Nuclear Engineering (ICONE25). American Society of Mechanical Engineers (ASME), Vol. 7.

    Research output: Chapters, Conference Papers, Creative and Literary WorksRGC 32 - Refereed conference paper (with host publication)peer-review

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  9. 2015
  10. Published

    Fully coupled multiphysics modeling of enhanced thermal conductivity UO2–BeO fuel performance in a light water reactor

    Liu, R., Zhou, W., Shen, P., Prudil, A. & Chan, P. K., 15 Dec 2015, In: Nuclear Engineering and Design. 295, p. 511-523

    Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 43
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