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
1 - 20 out of 23Page size: 20

Research Output

  1. 2025
  2. Published

    Research on key factors and mechanisms influencing geyser boiling in sodium heat pipes using a novel multiphase model

    Liu, J., Yu, D., Ali Shah, S. W., Chen, G., Li, T. & Pan, C., Feb 2025, In: Nuclear Engineering and Design. 432, 113795.

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

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  3. 2024
  4. Published

    Coupled neutronic-thermal–mechanical analysis of a medium temperature heat pipe cooled reactor

    Li, S. N., Huang, J. C., Yan, B. H. & Zhao, J. Y., May 2024, In: Nuclear Engineering and Design. 421, 113064.

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

    Scopus citations: 2
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  5. 2023
  6. Published

    Bubble transport during SGTR accident in lead-cooled fast reactor: A machine learning

    Dong, K., Ali Khan, S., He, S., Chen, J., Ding, P., Li, W. & Song, J. & 1 others, Zhao, J., 15 Dec 2023, In: Nuclear Engineering and Design. 415, 112724.

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

    Scopus citations: 1
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  7. Published

    Neutronic-coupled thermal hydraulic analysis of flow blockage in the hottest wire-wrapped LBE-cooled fuel assembly

    Xia, F., Liu, S., Li, T., Zeng, Q., Wang, Z., Dong, K. & Zhao, J., 1 Dec 2023, In: Nuclear Engineering and Design. 414, 112619.

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

    Scopus citations: 1
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  8. Published

    Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments

    Cheng, H., Chen, S., Huang, H., Cheng, S., Zhao, Z. & Zhao, J., Sept 2023, In: Nuclear Engineering and Design. 411, 112413.

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

    Scopus citations: 8
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  9. 2022
  10. Published

    Validation of thermal–hydraulic system code improved by advanced drift-flux correlation using bundle data at moderate pressure conditions

    Kinoshita, I. & Hibiki, T., Sept 2022, In: Nuclear Engineering and Design. 396, 111883.

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

    Scopus citations: 4
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  11. 2021
  12. Published

    Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels

    Ozaki, T. & Hibiki, T., 15 Dec 2021, In: Nuclear Engineering and Design. 385, 111502.

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

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  13. Published

    Thermal-hydraulic characteristics of upward two-phase flows in vertical large size square channels

    Hibiki, T., Katono, K. & Shen, X., 1 Dec 2021, In: Nuclear Engineering and Design. 384, 111490.

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

    Scopus citations: 5
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  14. Published

    Investigation of the effects of surface wettability and surface roughness on nanoscale boiling process using molecular dynamics simulation

    Liu, H., Deng, W., Ding, P. & Zhao, J., Oct 2021, In: Nuclear Engineering and Design. 382, 111400.

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

    Scopus citations: 24
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  15. Published

    Multiphysics analysis of thorium-based fuel performance under reactor normal operating and accident conditions in a light water reactor

    Qiu, C., Liu, R., Cai, J. & Zhou, W., 15 Apr 2021, In: Nuclear Engineering and Design. 375, 111096.

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

    Scopus citations: 9
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  16. 2019
  17. Published

    Pool boiling in seawater, NaCl solution and de-ionized water

    Huang, T.-C. & Pan, C., 1 Apr 2019, In: Nuclear Engineering and Design. 344, p. 46-53

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

    Scopus citations: 22
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  18. 2018
  19. 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 - Publication in refereed journal › peer-review

    Scopus citations: 36
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  20. 2016
  21. Published

    Transient LOFA computations for a VHTR using one-twelfth core flow models

    Tung, Y.-H., Ferng, Y.-M., Johnson, R. W. & Chieng, C.-C., 1 May 2016, In: Nuclear Engineering and Design. 301, p. 89-100

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

    Scopus citations: 12
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  22. 2015
  23. 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 - Publication in refereed journal › peer-review

    Scopus citations: 45
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  24. 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 - Publication in refereed journal › peer-review

    Scopus citations: 9
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  25. 2014
  26. 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 - Publication in refereed journal › peer-review

    Scopus citations: 9
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  27. Published

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

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

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

    Scopus citations: 21
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  28. 2013
  29. 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 - Publication in refereed journal › peer-review

    Scopus citations: 21
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  30. Published

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

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

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

    Scopus citations: 33
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  31. 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 - Publication in refereed journal › peer-review

    Scopus citations: 32
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