S M Kim
Engineering · Purdue University West Lafayette
Publications
13
Citations
29
Est. group size
~3
Recurring co-author estimate
Active years
19
Publishing since 2008
S M Kim works on nuclear reactor engineering topics, especially two-phase flow behavior (mixtures of gas and liquid) in pipes and reactor components, along with computational fluid dynamics (CFD) simulations of experimental reactor loops such as sodium and lead-bismuth eutectic systems. The research combines experimental measurements of pressure drop and flow patterns with simulation tools relevant to advanced and small modular reactor design. Some recent work also branches into unrelated areas like ferrofluid droplet dynamics and eye-tracking-based cognitive assessment, suggesting occasional interdisciplinary collaborations.
Publication output was absent for several years in the middle of the decade but has become more active and steady since 2024, with multiple outputs per year.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Small deformation theory for shape, rheology, and breakup of ferrofluid droplets in linear flow fields
Zenodo (CERN European Organization for Nuclear Research) · 2026
- A multidimensional eye-tracking assessment for estimating cognitive profiles in intellectual disability: A preliminary deep learning study
Digital Health · 2026
- RGB-based Two-phase Flow Classification Method Toward IAC Treatment in TRACE
Transactions of the American Nuclear Society · 2025
- Small Modular Reactors: Opportunities and Impacts for Indiana
Transactions of the American Nuclear Society · 2025
- Exploratory Experiments for Local Parameter Variations in Inclined Two-phase Flows
Transactions of the American Nuclear Society · 2025
- Analyzing Two-phase Frictional Pressure Losses in Horizontal and Vertical Straight Pipes
Transactions of the American Nuclear Society · 2025
- A Low-Cost Method for the Detection of Sub-picocurie per cc Concentrations of Ar-41 in Air
Transactions of the American Nuclear Society · 2024
- Investigation of Two-Phase Pressure Drop Across a Vertical U-Bend
Transactions of the American Nuclear Society · 2024
- Experimental Analysis of Air-Water Two-Phase Bubbly Flow Across a Vertical U-Bend
Transactions of the American Nuclear Society · 2024
- Scaling Analysis of the SFR Cartridge Loop
Transactions of the American Nuclear Society · 2020
- CFD Simulation of the LBE Loop in the Hybrid Fast and Thermal Subcritical Testbed
Transactions of the American Nuclear Society · 2020
- CFD Simulations of the Sodium Cartridge Loop of the Versatile Test Reactor
Transactions of the American Nuclear Society · 2020
- Transactions of the American Nuclear Society×10
- Zenodo (CERN European Organization for Nuclear Research)×1
- Digital Health×1
- Adam Dix
Engineering · Purdue University West Lafayette
- Mamoru Ishii
Engineering · Purdue University West Lafayette
- Zhuoran Dang
Engineering · Purdue University West Lafayette
- Seungjin Kim
Engineering · Purdue University West Lafayette
- Drew Ryan
Engineering · Purdue University West Lafayette
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 20, 2026.
Claim or correct this profile