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 80Page size: 20

Research Output

  1. 2024
  2. 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: 1
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  3. 2023
  4. 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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  5. 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

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  6. Optimized core design and shield analysis of a medium temperature heat pipe cooled reactor

    Li, S. N., Huang, J. C., Ma, B. B., Yan, B. H., Liang, Z. T. & Wang, L. S., 1 Dec 2023, In: Nuclear Engineering and Design. 414, 14 p., 112605.

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

    Scopus citations: 2
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  7. 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: 4
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  8. Effect of interfacial area modeling method on interfacial drag predictions for two-fluid model calculations in large diameter pipes

    Swearingen, A., Schlegel, J. P. & Hibiki, T., 1 Apr 2023, In: Nuclear Engineering and Design. 404, 112180.

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

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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: 3
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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: 21
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  15. Drift-flux parameter modeling of vertical downward gas–liquid two-phase flows for interfacial drag force formulation

    Dong, C. & Hibiki, T., Jul 2021, In: Nuclear Engineering and Design. 378, 111185.

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

    Scopus citations: 8
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  16. 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: 8
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  17. 2019
  18. 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: 20
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  19. 2018

  20. Axial development of gas-liquid flow regime maps in a vertical 5 × 5 rod bundle with prototypic spacer grids

    Liu, H., Pan, L.-M., Hibiki, T., Zhou, W.-X., Ren, Q.-Y. & Li, S.-S., 1 Dec 2018, In: Nuclear Engineering and Design. 339, p. 1-10

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

    Scopus citations: 9
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  21. Some characteristics of gas–liquid two-phase flow in vertical large-diameter channels

    Shen, X., Schlegel, J. P., Hibiki, T. & Nakamura, H., 1 Jul 2018, In: Nuclear Engineering and Design. 333, p. 87-98

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

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

    Scopus citations: 17
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  23. 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 - Publication in refereed journal › peer-review

    Scopus citations: 5
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  24. 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: 35
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  25. 2017

  26. A one-dimensional semi-empirical model considering transition boiling effect for dispersed flow film boiling

    Wang, Y.-J. & Pan, C., May 2017, In: Nuclear Engineering and Design. 316, p. 99-111

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

    Scopus citations: 3
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  27. An interfacial shear term evaluation study for adiabatic dispersed air–water two-phase flow with the two-fluid model using CFD

    Sharma, S. L., Hibiki, T., Ishii, M., Schlegel, J. P., Buchanan, J. R., Hogan, K. J. & Guilbert, P. W., 1 Feb 2017, In: Nuclear Engineering and Design. 312, p. 389-398

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

    Scopus citations: 19
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