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

Research Output

  1. 2017
  2. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 20
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  3. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 28
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  4. 2016
  5. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 8
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  6. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 5
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  7. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 27
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  8. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 26
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  9. Published

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

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

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

    Scopus citations: 12
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  10. The effect of external vertical acceleration on the dynamic behaviors of a single nuclear-coupled boiling channel

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

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

    Scopus citations: 10
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  11. 2015
  12. 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: 45
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  13. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 24
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  14. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 9
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  15. 2014
  16. Published

    Development of 3-D CFD methodology to investigate the transient thermal-hydraulic characteristics of coolant in a spent fuel pool

    Chen, S. R., Lin, W. C., Ferng, Y. M., Chieng, C. C. & Pei, B. S., Aug 2014, In: Nuclear Engineering and Design. 275, p. 272-280

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

    Scopus citations: 9
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  17. Published

    Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA

    Tung, Y.-H., Johnson, R. W., Ferng, Y.-M. & Chieng, C.-C., Aug 2014, In: Nuclear Engineering and Design. 275, p. 80-90

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

    Scopus citations: 20
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  18. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 18
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  19. Corrosion of Alloy 617 in high-temperature gas environments

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

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

    Scopus citations: 20
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  20. The oxidation effects of nuclear graphite during air-ingress accidents in HTGR

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

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

    Scopus citations: 30
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  21. 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 ReviewsRGC 21 - Publication in refereed journalpeer-review

    Scopus citations: 26
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  22. 2013
  23. Published

    Assessment of RELAP5/MOD3.3 condensation models for the tube bundle condensation in the PCCS of ESBWR

    Zhou, W., Wolf, B. & Revankar, S., Nov 2013, In: Nuclear Engineering and Design. 264, p. 111-118

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

    Scopus citations: 21
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  24. Published

    Study of natural circulation in a VHTR after a LOFA using different turbulence models

    Tung, Y.-H., Ferng, Y.-M., Johnson, R. W. & Chieng, C.-C., Oct 2013, In: Nuclear Engineering and Design. 263, p. 206-217

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

    Scopus citations: 33
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  25. Published

    Numerical simulation of the fluid-structure interaction for two simple fuel assemblies

    Liu, Z. G., Liu, Y. & Lu, J., May 2013, In: Nuclear Engineering and Design. 258, p. 1-12

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

    Scopus citations: 32
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