Nuclear Engineering and Design

Nuclear Engineering and Design

ISSNs: 0029-5493

Additional searchable ISSN (electronic): 1872-759X

Elsevier BV, Netherlands

Scopus rating (2023): CiteScore 3.4 SJR 0.83 SNIP 1.406

Journal

Journal Metrics
1 - 20 out of 58Page size: 20

Research Output

  1. 2023

  2. Optimized core design and shield analysis of a medium temperature heat pipe cooled reactor

    Li, S. N., Huang, J. C., Ma, B. B., Yan, B. H., Liang, Z. T. & Wang, L. S., 1 Dec 2023, In: Nuclear Engineering and Design. 414, 14 p., 112605.

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 2
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  3. Effect of interfacial area modeling method on interfacial drag predictions for two-fluid model calculations in large diameter pipes

    Swearingen, A., Schlegel, J. P. & Hibiki, T., 1 Apr 2023, In: Nuclear Engineering and Design. 404, 112180.

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

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  4. 2021

  5. 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 - Publication in refereed journal › peer-review

    Scopus citations: 7
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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 - Publication in refereed journal › peer-review

    Scopus citations: 8
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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 - Publication in refereed journal › peer-review

    Scopus citations: 12
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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 - Publication in refereed journal › peer-review

    Scopus citations: 17
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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 - Publication in refereed journal › peer-review

    Scopus citations: 4
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  11. 2017

  12. 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 - Publication in refereed journal › peer-review

    Scopus citations: 2
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  13. 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 - Publication in refereed journal › peer-review

    Scopus citations: 16
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  14. 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 - Publication in refereed journal › peer-review

    Scopus citations: 24
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  15. 2016

  16. 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 - Publication in refereed journal › peer-review

    Scopus citations: 8
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  17. 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 - Publication in refereed journal › peer-review

    Scopus citations: 5
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  18. 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 othersIreland, A., 15 Dec 2016, In: Nuclear Engineering and Design. 310, p. 638-647

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 22
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  19. 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 - Publication in refereed journal › peer-review

    Scopus citations: 26
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  20. 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 - Publication in refereed journal › peer-review

    Scopus citations: 10
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  21. 2015

  22. 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 - Publication in refereed journal › peer-review

    Scopus citations: 24
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  23. 2014

  24. The oxidation behavior of three different zones of welded Incoloy 800H alloy

    Chen, W. S., Kai, W., Tsay, L. W. & Kai, J. J., Jun 2014, In: Nuclear Engineering and Design. 272, p. 92-98

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 16
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  25. Corrosion of Alloy 617 in high-temperature gas environments

    Yeh, T., Chang, H., Wang, M., Yuan, T. & Kai, J., May 2014, In: Nuclear Engineering and Design. 271, p. 257-261

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 19
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  26. The oxidation effects of nuclear graphite during air-ingress accidents in HTGR

    Huang, W., Tsai, S., Chiu, I., Chen, C. & Kai, J., May 2014, In: Nuclear Engineering and Design. 271, p. 270-274

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 30
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  27. Interfacial area transport of subcooled boiling flow in a vertical annulus

    Brooks, C. S., Ozar, B., Hibiki, T. & Ishii, M., Mar 2014, In: Nuclear Engineering and Design. 268, p. 152-163

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 25
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