Nuclear Engineering and Design

Nuclear Engineering and Design

ISSNs: 0029-5493

Additional searchable ISSN (Electronic): 1872-759X

Elsevier BV, Netherlands

Scopus rating (2019): CiteScore 3.3 SJR 1.073 SNIP 1.328

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 journal

    Scopus citations: 2
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  3. 2018
  4. 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 journal

    Scopus citations: 5
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  5. 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 journal

    Scopus citations: 1
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  6. 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 journal

    Scopus citations: 12
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  7. 2017
  8. 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 journal

    Scopus citations: 1
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  9. 2016
  10. 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 journal

    Scopus citations: 6
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  11. 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 journal

    Scopus citations: 6
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  12. 2015
  13. 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 journal

    Scopus citations: 21
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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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journal

    Scopus citations: 5
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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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journal

    Scopus citations: 6
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  17. 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 journal

    Scopus citations: 12
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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 Reviews (RGC: 21, 22, 62)21_Publication in refereed journal

    Scopus citations: 10
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  19. 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 journal

    Scopus citations: 9
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  20. 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 journal

    Scopus citations: 16
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  21. 2013
  22. 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 journal

    Scopus citations: 10
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  23. 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 journal

    Scopus citations: 22
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  24. 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 journal

    Scopus citations: 13
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  25. 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 journal

    Scopus citations: 11
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  26. 2012
  27. 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 others, Bissett, 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 journal

    Scopus citations: 8
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  28. 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 journal

    Scopus citations: 13
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