| Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles—bundle friction factors, subchannel friction factors and mixing parameters SK Cheng, NE Todreas Nuclear engineering and design 92 (2), 227-251, 1986 | 511 | 1986 |
| Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles SK Chen, NE Todreas, NT Nguyen Nuclear Engineering and Design 267, 109-131, 2014 | 107 | 2014 |
| The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles SK Chen, YM Chen, NE Todreas Nuclear Engineering and Design 335, 356-373, 2018 | 96 | 2018 |
| Constitutive correlations for wire-wrapped subchannel analysis under forced and mixed convection conditions S Zheng Massachusetts Institute of Technology, 1984 | 77 | 1984 |
| Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region SK Chen, R Petroski, NE Todreas Nuclear Engineering and Design 263, 406-410, 2013 | 39 | 2013 |
| Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD) J Pacio, SK Chen, YM Chen, NE Todreas Nuclear Engineering and Design 388, 111607, 2022 | 19 | 2022 |
| Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data J Pacio, SK Chen, YM Chen, NE Todreas Nuclear Engineering and Design 388, 111606, 2022 | 10 | 2022 |
| A note on the accuracy of the upgraded Cheng and Todreas correlation for predicting pressure drop in hexagonal bare rod bundles SK Chen, YM Chen, NE Todreas Applied Thermal Engineering 161, 114193, 2019 | 9 | 2019 |
| Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients NE Todreas, SK Cheng, K Basehore Massachusetts Inst. of Tech. Report, 1984 | 8 | 1984 |
| Adventures in study of the pressure losses in wire-wrapped rod bundle arrays N Todreas, SK Chen, J Pacio Nuclear Engineering and Design 370, 110910, 2020 | 6 | 2020 |
| Energy transfer mechanisms under mixed convection conditions in LMFBR wire-wrapped bundles S Cheng, TS Ro, NE Todreas Proceedings of third international topical meeting on reactor thermal hydraulics, 1985 | 6 | 1985 |
| Development of a MELCOR self-initialization algorithm for boiling water reactors CS Chien, SJ Wang, SK Cheng Nuclear technology 113 (1), 21-28, 1996 | 5 | 1996 |
| The current status of TRR-II project S Chou, Y Ma, J Yang, K Tu, D Lee, K Lan, S Chen | 3 | 2001 |
| Corrigendum to “The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles”[Nucl. Eng. Des. 335 (2018) 356–373] SK Chen, YM Chen, NE Todreas Nuclear Engineering and Design 340, 414, 2018 | 1 | 2018 |
| Development of Dynamic Event Tree for Steam Generator Tube Rupture of a PWR CJ Chang, CC Chao, SK Chen Proc. Int. Conf. Nuclear Engineering, San Diego, California, 1998 | 1 | 1998 |
| Seal loss-of-coolant accident and recovery actions following loss of component cooling water SK Cheng Nuclear Technology 84 (3), 305-314, 1989 | 1 | 1989 |
| Corrigendum to “Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: the Pacio-Chen-Todreas Detailed model (PCTD … J Pacio, SK Chen, YM Chen, NE Todreas Nuclear Engineering and Design 395, 111846, 2022 | | 2022 |
| Effect of Power Uprate on Core Damage Frequency in a MBLOCA with Multiple Operator Actions C Y. M. Chen, M. Lee, S. K Annals of Nuclear Energy 109, 350-358, 2017 | | 2017 |
| CONTAINMENT AND RELEASE CATEGORY ANALYSES FOR A BWR-4 REACTOR WITH MARK-I CONTAINMENT SK Cheng, YC Chou, TJ Lin, YH Yang, AE Council PSA'93: proceedings of the International Topical Meeting on Probabilistic …, 1993 | | 1993 |
| INSIGHTS GAINED FROM CHINSHAN LIVING PRA MODEL IN TAIWAN TJ Lin, GD Li, SK Cheng, AE Council PSA'93: proceedings of the International Topical Meeting on Probabilistic …, 1993 | | 1993 |
