Author

Michael Y. Young

Observed names: M. Y. Young, M.Y Young, M.Y. Young, Michael Y. YOUNG, Young, M. Y. author.

Institution: University of Michigan

Observed institutions: University of Michigan, Westinghouse Electric (United States)

OpenAlex ID: A5111496657

Application of code scaling applicability and uncertainty methodology to the large break loss of coolant

1998 · M.Y. Young, S.M. Bajorek, et al. · Nuclear Engineering and Design · 56

On the factors affecting the fretting-wear risk of PWR fuel assemblies

2008 · Pablo R. Rubiolo, Michael Y. Young · Nuclear Engineering and Design · 51

Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data

1999 · K Takeuchi, M.Y Young, et al. · Nuclear Engineering and Design · 30

Flow Induced Vibration and Fretting Wear in PWR Fuel

2002 · S. J. King, M. Y. Young, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 21

Generalized Drift Flux Correlation for Vertical Flow

1992 · Kenji Takeuchi, Michael Y. Young, et al. · Nuclear Science and Engineering · 20

Direct-Contact Heat Transfer Model for Dispersed-Flow Film Boiling

2000 · Stephen M. Bajorek, Michael Y. Young · Nuclear Technology · 17

VITRAN: an Advance Statistic Tool to Evaluate Fretting-wear Damage

2008 · Pablo R. RUBIOLO, Michael Y. YOUNG · Journal of Power and Energy Systems · 15

PDF

Westinghouse Advanced Loop Tester (WALT) Update

2008 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 13

Simulation of PWR Crud

2014 · W. A. Byers, G. Wang, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 12

Thermal Conductivity Measurements for Simulated PWR Crud

2013 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 11

Reactor Operations

2020 · Michael Y. Young · Elsevier eBooks · 7

Single Rod Heat Transfer Tests to Study the Effects of Crud Deposition

2006 · G. Wang, W. A. Byers, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 7

Application of Realistic Thermal-Hydraulic Methods for Pressurized Water Reactors with Upper Plenum Injection

1989 · Thomas M. Parker, Richard J. Kohrt, et al. · Nuclear Technology · 6

SATAN VI program: comprehensive space--time dependent analysis of loss-of- coolant

1974 · F.M. Bordelon, Robert D. Kelly, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 6

Characterization of Unsteady Core Flow Patterns through Noise Analysis Techniques

2008 · Pablo R. RUBIOLO, Michael Y. YOUNG · Journal of Power and Energy Systems · 5

PDF

Fuel Rod, Fuel Assembly, and Reactivity Control Assembly Design

2020 · Michael Y. Young · Elsevier eBooks · 4

Methods to Reduce CIPS/CILC Risk for the Zero Fuel Failure by 2010 Initiative

2010 · Guoqiang Wang, Michael Y. Young, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 4

Application of CFD Model for Inlet Flow Region of 17×17 Fuel Assembly

2006 · Milorad B. Dzodzo, Bin Liu, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 4

Application of PWR LOCA margin with the revised Appendix K rule

1992 · L.E. Hochreiter, R.D. Ankney, et al. · Nuclear Engineering and Design · 4

A Method of Computing Hydraulic Reaction Force Due to a Fluid Jet at a Steamline Break

1986 · S. Abedin, K. Takeuchi, et al. · Nuclear Science and Engineering · 4

Cardiomyocyte Janus kinase 1 (JAK1) signaling is required for cardiac homeostasis and cytokine-dependent activation of STAT3

2025 · Arasakumar Subramani, Kobina Essandoh, et al. · Journal of Molecular and Cellular Cardiology · 3

ICONE15-10665 VIPRE-01/BOA Modeling of Westinghouse Advanced Loop Tester (WALT)

2007 · G. Wang, M. Y. Young, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3

PDF

On the Factors Affecting the Fretting-Wear Risk of PWR Fuel Assemblies

2006 · Pablo R. Rubiolo, Michael Y. Young · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3

CFD approach for investigating flow and heat transfer in PWR fuel assembly

2005 · B. Liu, R.P. Knott, et al. · 3

Flow Induced Vibration and Fretting Wear: An Integrated Approach

2002 · D. V. Paramonov, S. J. King, et al. · ASME International Symposium on Fluid-Structure Interactions, Flow-Sound Interactions, and Flow-Induced Vibration and Noise · 3

Works count: 54

Citation count: 332

H-index: 10

I10-index: 10