Nuclear Engineering and Design

Nuclear Engineering and Design

ISSNs: 0029-5493

Additional searchable ISSN (Electronic): 1872-759X

Elsevier BV, Netherlands

Scopus rating (2022): CiteScore 3.4 SJR 0.853 SNIP 1.234

Journal

Journal Metrics

Research Output

  1. 2016
  2. 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, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 18
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  3. 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: 25
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  4. 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: 11
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  5. 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: 9
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  6. 2015
  7. 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: 37
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  8. 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: 22
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  9. 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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  10. 2014
  11. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 8
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  12. Published

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

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

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

    Scopus citations: 18
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  13. 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, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 14
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  14. 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, 22, 62)21_Publication in refereed journalpeer-review

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

    Scopus citations: 28
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  16. 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, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 23
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  17. 2013
  18. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 17
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  19. Published

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

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

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

    Scopus citations: 31
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  20. 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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

    Scopus citations: 24
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  21. Counterpart experimental study of ISP-42 PANDA tests on PUMA facility

    Yang, J., Choi, S., Lim, J., Lee, D., Rassame, S., Hibiki, T. & Ishii, M., 2013, In: Nuclear Engineering and Design. 258, p. 249-257

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

    Scopus citations: 10
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  22. Experimental stability maps for a two-phase natural circulation reactor with and without void-reactivity feedback effect

    Dixit, A., Hibiki, T., Ishii, M., Tanimoto, K., Kondoh, Y. & Hibi, K., 2013, In: Nuclear Engineering and Design. 261, p. 181-200

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

    Scopus citations: 11
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  23. Investigation of one-dimensional interfacial area transport for vertical upward air-water two-phase flow in an annular channel at elevated pressures

    Ozar, B., Brooks, C. S., Euh, D. J., Hibiki, T. & Ishii, M., 2013, In: Nuclear Engineering and Design. 263, p. 362-379

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

    Scopus citations: 12
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  24. Modified distribution parameter for churn-turbulent flows in large diameter channels

    Schlegel, J. P., Macke, C. J., Hibiki, T. & Ishii, M., 2013, In: Nuclear Engineering and Design. 263, p. 138-150

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

    Scopus citations: 21
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