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
Research Output
- 2023
- 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, 22, 62) › 21_Publication in refereed journal › peer-review
- 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, 22, 62) › 21_Publication in refereed journal › peer-review
- 2022
- 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, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 2 - 2021
- 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, 22, 62) › 21_Publication in refereed journal › peer-review
- 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, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 1 - 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, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 6 - 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, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 4 - 2019
- 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. 46-53Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 15 - 2018
- 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. 106-116Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 27 - 2016
- 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. 89-100Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 11 - 2015
- 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. 511-523Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 37 - 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. 284-292Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 8 - 2014
- 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. 272-280Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 8 - 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. 80-90Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 18 - 2013
- 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. 111-118Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 17 - 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. 206-217Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 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. 1-12Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 24 - 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. 77-86Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 18 - 2012
- 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. 285-293Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 18 - 2011
- 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. 3613-3623Research output: Journal Publications and Reviews (RGC: 21, 22, 62) › 21_Publication in refereed journal › peer-review
Scopus citations: 6