Nuclear Engineering and Design

Nuclear Engineering and Design

ISSNs: 0029-5493

Additional searchable ISSN (Electronic): 1872-759X

Elsevier BV, Netherlands

Scopus rating (2021): CiteScore 2.9

Journal

Journal Metrics

Research Output

  1. 2021
  2. Drift-flux parameter modeling of vertical downward gas–liquid two-phase flows for interfacial drag force formulation

    Dong, C. & Hibiki, T., Jul 2021, In: Nuclear Engineering and Design. 378, 111185.

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

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  3. 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: 1
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  4. 2019
  5. Published

    Pool boiling in seawater, NaCl solution and de-ionized water

    Huang, T. & Pan, C., 1 Apr 2019, In: Nuclear Engineering and Design. 344, p. 46-53

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

    Scopus citations: 8
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  6. 2018
  7. Axial development of gas-liquid flow regime maps in a vertical 5 × 5 rod bundle with prototypic spacer grids

    Liu, H., Pan, L., Hibiki, T., Zhou, W., Ren, Q. & Li, S., 1 Dec 2018, In: Nuclear Engineering and Design. 339, p. 1-10

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

    Scopus citations: 2
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  8. Some characteristics of gas–liquid two-phase flow in vertical large-diameter channels

    Shen, X., Schlegel, J. P., Hibiki, T. & Nakamura, H., 1 Jul 2018, In: Nuclear Engineering and Design. 333, p. 87-98

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

    Scopus citations: 5
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  9. Hybrid fuzzy-PID control of a nuclear Cyber-Physical System working under varying environmental conditions

    Wang, W., Di Maio, F. & Zio, E., May 2018, In: Nuclear Engineering and Design. 331, p. 54-67

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

    Scopus citations: 9
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  10. Application of NUREG/CR-6850 to the fire risk quantification of a High Temperature Gas-Cooled Reactor

    Wang, W., Tong, J. & Zhao, J., 15 Apr 2018, In: Nuclear Engineering and Design. 330, p. 332-343

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

    Scopus citations: 2
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  11. Published

    Multiphysics modeling of accident tolerant fuel-cladding U3Si2-FeCrAl performance in a light water reactor

    Liu, R., Zhou, W. & Cai, J., 15 Apr 2018, In: Nuclear Engineering and Design. 330, p. 106-116

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

    Scopus citations: 16
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  12. 2017
  13. A one-dimensional semi-empirical model considering transition boiling effect for dispersed flow film boiling

    Wang, Y. & Pan, C., May 2017, In: Nuclear Engineering and Design. 316, p. 99-111

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

    Scopus citations: 1
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  14. An interfacial shear term evaluation study for adiabatic dispersed air–water two-phase flow with the two-fluid model using CFD

    Sharma, S. L., Hibiki, T., Ishii, M., Schlegel, J. P., Buchanan, J. R., Hogan, K. J. & Guilbert, P. W., 1 Feb 2017, In: Nuclear Engineering and Design. 312, p. 389-398

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

    Scopus citations: 8
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  15. Turbulence-induced bubble collision force modeling and validation in adiabatic two-phase flow using CFD

    Sharma, S. L., Hibiki, T., Ishii, M., Brooks, C. S., Schlegel, J. P., Liu, Y. & Buchanan, J. R., 1 Feb 2017, In: Nuclear Engineering and Design. 312, p. 399-409

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

    Scopus citations: 10
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  16. 2016
  17. Characteristics of two-phase flows in large diameter channels

    Schlegel, J. P., Hibiki, T. & Ishii, M., 15 Dec 2016, In: Nuclear Engineering and Design. 310, p. 544-551

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

    Scopus citations: 5
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  18. Interfacial area transport due to shear collision of bubbly flow in small-diameter pipes

    Hazuku, T., Hibiki, T. & Takamasa, T., 15 Dec 2016, In: Nuclear Engineering and Design. 310, p. 592-603

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

    Scopus citations: 4
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  19. Prediction of interfacial area transport in a scaled 8×8 BWR rod bundle

    Yang, X., Schlegel, J. P., Liu, Y., Paranjape, S., Hibiki, T., Ishii, M., Bajorek, S. & 1 others, Ireland, A., 15 Dec 2016, In: Nuclear Engineering and Design. 310, p. 638-647

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

    Scopus citations: 12
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  20. Flow regime, void fraction and interfacial area transport and characteristics of co-current downward two-phase flow

    Lokanathan, M. & Hibiki, T., 1 Oct 2016, In: Nuclear Engineering and Design. 307, p. 39-63

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

    Scopus citations: 19
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  21. Published

    Transient LOFA computations for a VHTR using one-twelfth core flow models

    Tung, Y., Ferng, Y., Johnson, R. W. & Chieng, C., 1 May 2016, In: Nuclear Engineering and Design. 301, p. 89-100

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

    Scopus citations: 8
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  22. The effect of external vertical acceleration on the dynamic behaviors of a single nuclear-coupled boiling channel

    Lee, J., Chen, S. & Pan, C., May 2016, In: Nuclear Engineering and Design. 301, p. 264-278

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

    Scopus citations: 8
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  23. 2015
  24. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 27
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  25. Two-group modeling of interfacial area transport in large diameter channels

    Schlegel, J. P., Hibiki, T. & Ishii, M., 1 Nov 2015, In: Nuclear Engineering and Design. 293, p. 75-86

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

    Scopus citations: 15
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  26. Published

    Development of CFD methodology for investigating thermal-hydraulic characteristics in a PWR dome

    Cheng, W. C., Ferng, Y. M., Chen, S. R. & Chieng, C. C., 1 Apr 2015, In: Nuclear Engineering and Design. 284, p. 284-292

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

    Scopus citations: 8
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