Nuclear Engineering and Design

Nuclear Engineering and Design

ISSNs: 0029-5493

Additional searchable ISSN (Electronic): 1872-759X

Elsevier BV, Netherlands

Scopus rating (2018): CiteScore 1.85 SJR 1.304 SNIP 1.61

Journal

Journal Metrics

Research Output

  1. 2019
  2. 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 journalNot applicablepeer-review

    Scopus citations: 2
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  3. 2018
  4. 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 journalNot applicablepeer-review

    Scopus citations: 6
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  5. 2017
  6. 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 journalNot applicablepeer-review

    Scopus citations: 1
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  7. 2016
  8. 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 journalNot applicablepeer-review

    Scopus citations: 4
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  9. 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 journalNot applicablepeer-review

    Scopus citations: 6
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  10. 2015
  11. 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 journalNot applicablepeer-review

    Scopus citations: 18
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  12. 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 journalNot applicablepeer-review

    Scopus citations: 4
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  13. 2014
  14. 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 journalNot applicablepeer-review

    Scopus citations: 5
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  15. 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 journalNot applicablepeer-review

    Scopus citations: 12
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  16. 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 journalNot applicablepeer-review

    Scopus citations: 7
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  17. 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 journalNot applicablepeer-review

    Scopus citations: 9
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  18. 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 journalNot applicablepeer-review

    Scopus citations: 12
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  19. 2013
  20. 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 journalNot applicablepeer-review

    Scopus citations: 8
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  21. 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 journalNot applicablepeer-review

    Scopus citations: 19
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  22. 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 journalNot applicablepeer-review

    Scopus citations: 13
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  23. Published

    Numerical computations on flow and heat transfer characteristics of a helically coiled heat exchanger using different turbulence models

    Lin, W., Ferng, Y. & Chieng, C., 2013, In : Nuclear Engineering and Design. 263, p. 77-86

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

    Scopus citations: 9
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  24. 2012
  25. Study of impact of the AP1000® reactor vessel upper internals design on fuel performance

    Xu, Y., Conner, M., Yuan, K., Dzodzo, M. B., Karoutas, Z., Beltz, S. A., Ray, S. & 4 othersBissett, T. A., Chieng, C., Kao, M. & Wu, C., Nov 2012, In : Nuclear Engineering and Design. 252, p. 128-134

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

    Scopus citations: 7
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  26. Published

    CFD analysis for full vessel upper plenum in Maanshan Nuclear Power Plant

    Wu, C. Y., Ferng, Y. M., Chieng, C. C. & Kang, Z. C., 2012, In : Nuclear Engineering and Design. 253, p. 285-293

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

    Scopus citations: 12
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  27. 2011
  28. CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models

    Kao, M., Wu, C., Chieng, C., Xu, Y., Yuan, K., Dzodzo, M., Conner, M. & 3 othersBeltz, S., Ray, S. & Bissett, T., Oct 2011, In : Nuclear Engineering and Design. 241, 10, p. 4181-4193

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

    Scopus citations: 20
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  29. Published

    Transient thermal stress intensity factors for Mode i edge-cracks

    Zhou, Z., Xu, X., Leung, A. Y. & Guan, Z., Sep 2011, In : Nuclear Engineering and Design. 241, 9, p. 3613-3623

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

    Scopus citations: 3
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