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. 2013
  2. 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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  3. 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 journalpeer-review

    Scopus citations: 18
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  4. Start-up transient test simulation with and without void-reactivity feedback for a two-phase natural circulation reactor

    Dixit, A., Hibiki, T., Ishii, M., Tanimoto, K., Kondoh, Y. & Hibi, K., 2013, In: Nuclear Engineering and Design. 265, p. 1131-1147

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

    Scopus citations: 15
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  5. 2012
  6. 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 journalpeer-review

    Scopus citations: 11
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  7. Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation

    Yang, J., Choi, S., Lim, J., Lee, D., Rassame, S., Hibiki, T. & Ishii, M., Jun 2012, In: Nuclear Engineering and Design. 247, p. 128-135

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

    Scopus citations: 16
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  8. 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 journalpeer-review

    Scopus citations: 18
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  9. 2011
  10. 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 journalpeer-review

    Scopus citations: 26
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  11. Published

    Transient thermal stress intensity factors for Mode i edge-cracks

    Zhou, Z., Xu, X., Leung, A. Y. & Guan, Z., Sept 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 journalpeer-review

    Scopus citations: 6
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  12. SCWR single channel stability analysis using a response matrix method

    Zhao, J., Tso, C. P. & Tseng, K. J., Jul 2011, In: Nuclear Engineering and Design. 241, 7, p. 2528-2535

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

    Scopus citations: 27
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  13. 2010
  14. Heat transfer deterioration in a supercritical water channel

    Kao, M., Lee, M., Ferng, Y. & Chieng, C., Oct 2010, In: Nuclear Engineering and Design. 240, 10, p. 3321-3328

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

    Scopus citations: 49
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  15. Modeling and measurement of interfacial area concentration in two-phase flow

    Paranjape, S., Ishii, M. & Hibiki, T., Sept 2010, In: Nuclear Engineering and Design. 240, 9, p. 2329-2337

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

    Scopus citations: 40
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  16. Investigating the advantages and disadvantages of realistic approach and porous approach for closely packed pebbles in CFD simulation

    Wu, C. Y., Ferng, Y. M., Chieng, C. C. & Liu, C. C., May 2010, In: Nuclear Engineering and Design. 240, 5, p. 1151-1159

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

    Scopus citations: 61
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  17. 2009
  18. Void fraction and flow regime in adiabatic upward two-phase flow in large diameter vertical pipes

    Schlegel, J. P., Sawant, P., Paranjape, S., Ozar, B., Hibiki, T. & Ishii, M., Dec 2009, In: Nuclear Engineering and Design. 239, 12, p. 2864-2874

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

    Scopus citations: 103
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  19. Scaling of passive condenser system for separate effect testing

    Revankar, S. T., Oh, S., Zhou, W. & Henderson, G., Oct 2009, In: Nuclear Engineering and Design. 239, 10, p. 1870-1878

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

    Scopus citations: 4
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  20. Formulation of time and volume averaged two-fluid model considering structural materials in a control volume

    Lee, S. Y., Hibiki, T. & Ishii, M., Jan 2009, In: Nuclear Engineering and Design. 239, 1, p. 127-139

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

    Scopus citations: 13
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  21. 2008
  22. Small punch testing for assessing the fracture properties of the reactor vessel steel with different thicknesses

    Wang, Z., Shi, H., Lu, J., Shi, P. & Ma, X., Dec 2008, In: Nuclear Engineering and Design. 238, 12, p. 3186-3193

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

    Scopus citations: 65
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  23. 2005
  24. Dynamic analysis of multiple nuclear-coupled boiling channels based on a multi-point reactor model

    Der Lee, J. & Pan, C., Nov 2005, In: Nuclear Engineering and Design. 235, 22, p. 2358-2374

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

    Scopus citations: 28
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  25. Nonlinear analysis for a nuclear-coupled two-phase natural circulation loop

    Lee, J. D. & Pan, C., Feb 2005, In: Nuclear Engineering and Design. 235, 5, p. 613-626

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

    Scopus citations: 47
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  26. 2001
  27. Effect of inlet geometry on hot-leg U-bend two-phase natural circulation in a loop with a large diameter pipe

    Hibiki, T. & Ishii, M., 2 Jan 2001, In: Nuclear Engineering and Design. 203, 2-3, p. 209-228

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

    Scopus citations: 18
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  28. Flow regime transition criteria for upward two-phase flow in vertical narrow rectangular channels

    Hibiki, T. & Mishima, K., 2 Jan 2001, In: Nuclear Engineering and Design. 203, 2-3, p. 117-131

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

    Scopus citations: 129
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