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
41 - 60 out of 81Page size: 20

Research Output

  1. 2013

  2. Counterpart experimental study of ISP-42 PANDA tests on PUMA facility

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

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 12
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  3. 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 - Publication in refereed journal › peer-review

    Scopus citations: 11
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  4. 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 - Publication in refereed journal › peer-review

    Scopus citations: 12
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  5. 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 - Publication in refereed journal › peer-review

    Scopus citations: 23
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  6. Published

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

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

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 21
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  7. 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 - Publication in refereed journal › peer-review

    Scopus citations: 15
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  8. 2012

  9. 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.-C., Kao, M.-T. & Wu, C.-Y., Nov 2012, In: Nuclear Engineering and Design. 252, p. 128-134

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 12
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  10. Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation

    Yang, J., Choi, S.-W., Lim, J., Lee, D.-Y., 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 - Publication in refereed journal › peer-review

    Scopus citations: 16
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  11. 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 - Publication in refereed journal › peer-review

    Scopus citations: 19
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  12. 2011

  13. CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models

    Kao, M.-T., Wu, C.-Y., Chieng, C.-C., Xu, Y., Yuan, K., Dzodzo, M. & Conner, M. & 3 others, Beltz, 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 - Publication in refereed journal › peer-review

    Scopus citations: 27
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  14. Published

    Transient thermal stress intensity factors for Mode i edge-cracks

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

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 6
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  15. 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 - Publication in refereed journal › peer-review

    Scopus citations: 29
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  16. 2010

  17. Heat transfer deterioration in a supercritical water channel

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

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 51
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  18. 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 - Publication in refereed journal › peer-review

    Scopus citations: 44
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  19. 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 - Publication in refereed journal › peer-review

    Scopus citations: 69
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  20. 2009

  21. 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 - Publication in refereed journal › peer-review

    Scopus citations: 114
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  22. 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 - Publication in refereed journal › peer-review

    Scopus citations: 4
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  23. 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 - Publication in refereed journal › peer-review

    Scopus citations: 13
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  24. 2008

  25. Small punch testing for assessing the fracture properties of the reactor vessel steel with different thicknesses

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

    Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review

    Scopus citations: 76
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  26. 2005

  27. 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 - Publication in refereed journal › peer-review

    Scopus citations: 29
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