Mamoru Ishii
Engineering · Purdue University West Lafayette
Publications
273
Citations
16,066
Est. group size
~2
Recurring co-author estimate
Active years
56
Publishing since 1970
Mamoru Ishii's research focuses on multiphase (gas-liquid) flow behavior, especially as it relates to boiling and two-phase flow in nuclear reactor systems and other engineering applications. Work includes experimental studies of bubble and flow patterns, mathematical and computational modeling of flow structures, and the use of machine learning tools to classify and predict flow behavior. This research supports the design and safety analysis of nuclear reactors and thermal systems that rely on liquid-vapor mixtures.
Publication output has declined from around 9 papers per year in 2017 to roughly 2-4 per year in recent years, though 2025 shows a modest uptick.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Characterization of departure diameter, departure frequency and active nucleation site density in subcooled boiling flow
Applied Thermal Engineering · 2025
- Assessment of TRACE for predicting startup transients in natural circulation boiling water reactors
Nuclear Engineering and Design · 2025
- CNN-BiLSTM: A hybrid deep learning approach for annular flow regime identification in 1-inch round pipe geometry
SSRN Electronic Journal · 2025
- 宇宙天気に関する国際動向
Institutional Repositories DataBase (IRDB) · 2025
- Neural network based two-phase flow classification in a vertical narrow rectangular channel
International Journal of Multiphase Flow · 2024
- Modeling and simulation of cryogenic propellant tank pressurization in normal gravity
Applied Thermal Engineering · 2023
- Investigation of nucleate boiling and bubble dynamics at multiple nucleation sites in subcooled boiling flow
International Journal of Heat and Mass Transfer · 2023
- Advanced Instrumentation and Modeling Framework for Two-Phase Flow
Nuclear Technology · 2023
- Experiment and Modeling of Interfacial Area Concentration of Liquid Film in Upward Annular Two-Phase Flow
Nuclear Technology · 2023
- Towards stochastic modeling for two-phase flow interfacial area predictions: A physics-informed reinforcement learning approach
International Journal of Heat and Mass Transfer · 2022
- Experimental investigation on flashing-induced flow instability in a natural circulation scaled-down test facility
Annals of Nuclear Energy · 2022
- Progress in two-phase flow modeling: Interfacial area transport
Nuclear Engineering and Design · 2021
- Experimental study of bubble size distribution in bubbly and bubbly-to-slug transition flow
International Journal of Multiphase Flow · 2021
- Comprehensive evaluation of two-group interfacial area transport equation and new intergroup transfer model
International Journal of Heat and Mass Transfer · 2021
- Assessment of Nucleation Boiling Models and Improvement by the Chen Correlation for Two-fluid Model CFD
International Journal of Heat and Mass Transfer · 2021
- International Journal of Heat and Mass Transfer×13
- Annals of Nuclear Energy×9
- International Journal of Multiphase Flow×6
- Nuclear Engineering and Design×6
- Applied Thermal Engineering×3
- Seungjin Kim
Engineering · Purdue University West Lafayette
- Zhuoran Dang
Engineering · Purdue University West Lafayette
- Seungjin Kim
Engineering · Purdue University West Lafayette
- Martín López de Bertodano
Engineering · Purdue University West Lafayette
- Adam Dix
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