Dr. ZHOU Wenzhong (周文忠)

Research Output

  1. 2021
  2. Online published

    Multiphysics analysis of thorium-based fuel performance with a two-layer SiC cladding under normal operating and transient conditions in a light water reactor

    Qiu, C., Liu, R., Cai, J. & Zhou, W., 1 Dec 2021, In: Annals of Nuclear Energy. 163, 108543.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  3. Published

    Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

    Lu, W., Qian, L. & Zhou, W., Jun 2021, In: Frontiers in Energy Research. 9, 667419.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  4. Published

    Multiphysics Investigation on Coolant Thermohydraulic Conditions and Fuel Rod Behavior During a Loss-of-Coolant Accident

    Yu, M., Qian, L. & Zhou, W., Jun 2021, In: Frontiers in Energy Research. 9, 691813.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  5. Published

    Multiphysics Modeling of Thorium-Based Fuel Performance With Cr-Coated SiC/SiC Composite Under Normal and Accident Conditions

    Liu, S., Liu, R., Qiu, C. & Zhou, W., Jun 2021, In: Frontiers in Energy Research. 9, 677606.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  6. Published

    Multiphysics analysis of thorium-based fuel performance under reactor normal operating and accident conditions in a light water reactor

    Qiu, C., Liu, R., Cai, J. & Zhou, W., 15 Apr 2021, In: Nuclear Engineering and Design. 375, 111096.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 2
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  7. 2020
  8. Published

    Multiphysics Analysis of Thorium-Based Fuel Performance Under Reactor Steady-State and Transient Accident

    Qiu, C., Liu, R. & Zhou, W., Aug 2020, Proceedings of the 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference: Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering. American Society of Mechanical Engineers (ASME), Vol. 1. V001T05A010. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 1).

    Research output: Chapters, Conference Papers, Creative and Literary Works (RGC: 12, 32, 41, 45)32_Refereed conference paper (with ISBN/ISSN)peer-review

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  9. Published

    Numerical investigation of nucleate pool boiling outside a vertical tube under sub-atmospheric pressures

    Ren, S. & Zhou, W., Jul 2020, In: International Communications in Heat and Mass Transfer. 116, 104662.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  10. Published

    Pre-CHF boiling heat transfer performance on tube bundles with or without enhanced surfaces - a review

    Ren, S. & Zhou, W., May 2020, In: Annals of Nuclear Energy. 139, 107278.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 1
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  11. Published

    Multiphysics modeling of thorium-based fuel performance with a two-layer SiC cladding in a light water reactor

    Liu, R., Cai, J. & Zhou, W., Feb 2020, In: Annals of Nuclear Energy. 136, 107036.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 8
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  12. 2019
  13. Published

    Numerical Investigation on Pool Boiling Over a Vertical Tube Coupled With In-Tube Condensation

    Ren, S. & Zhou, W., Jul 2019, ASME 2019 Heat Transfer Summer Conference: collocated with the ASME 2019 13th International Conference on Energy Sustainability. American Society of Mechanical Engineers (ASME), HT2019-3442, V001T10A001. (ASME Heat Transfer Summer Conference).

    Research output: Chapters, Conference Papers, Creative and Literary Works (RGC: 12, 32, 41, 45)32_Refereed conference paper (with ISBN/ISSN)peer-review

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  14. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 1
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  15. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 4
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  16. 2018
  17. Published

    Elemental phase partitioning in the γ - γ" Ni2CoFeCrNb0.15 high entropy alloy

    Han, B., Wei, J., He, F., Chen, D., Wang, Z. J., Hu, A., Zhou, W. & 1 others, Kai, J. J., Dec 2018, In: Entropy. 20, 12, 910.

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 5
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  18. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 7
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  19. Published

    Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review

    Zhou, W. & Zhou, W., Sep 2018, In: Annals of Nuclear Energy. 119, p. 66-86

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 35
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  20. Published

    Multiphysics modeling of fabrication methods' effect on UO2-BEO composite fuels' performance

    Zhou, W. & Zhou, W., Jul 2018, ASME Proceedings - Student Paper Competition. American Society of Mechanical Engineers (ASME), Vol. 9. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 9).

    Research output: Chapters, Conference Papers, Creative and Literary Works (RGC: 12, 32, 41, 45)32_Refereed conference paper (with ISBN/ISSN)peer-review

    Check@CityULib
  21. Published

    Multiphysics modeling of thorium-based (Th, u)O2 and (Th, PU)O2 fuel performance in a light water reactor

    Liu, R., Cai, J., Zhou, W. & Wang, Y., Jul 2018, ASME Proceedings - Nuclear Fuel and Material, Reactor Physics, and Transport Theory. American Society of Mechanical Engineers (ASME), Vol. 3. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 3).

    Research output: Chapters, Conference Papers, Creative and Literary Works (RGC: 12, 32, 41, 45)32_Refereed conference paper (with ISBN/ISSN)peer-review

    Scopus citations: 1
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  22. 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 Works (RGC: 12, 32, 41, 45)32_Refereed conference paper (with ISBN/ISSN)peer-review

    Check@CityULib
  23. Published

    Solid Mechanics Behavior of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, FeCrAl and Surface-Coated Claddings

    Zhou, W. & Zhou, W., Jun 2018, In: Transactions of the American Nuclear Society. 118, p. 1430-1432

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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  24. Published

    Microstructure Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO

    Zhou, W., Revankar, S. T., Liu, R. & Shahmohammadi Beni, M., May 2018, In: Heat Transfer Engineering. 39, 9, p. 760-774

    Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 8
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