Mamoru Ishii

Mamoru Ishii

Purdue University

H-index: 78

North America-United States

About Mamoru Ishii

Mamoru Ishii, With an exceptional h-index of 78 and a recent h-index of 45 (since 2020), a distinguished researcher at Purdue University, specializes in the field of Two-phase flow, Nuclear Engineering, Thermal Hydraulics, Safety Analysis, Two-fluid Model Development.

His recent articles reflect a diverse array of research interests and contributions to the field:

Razvoj i primena dvostruke elektrootporne sonde za merеnjа u strujnim višejaznim sistemima

An Equation-Free Based Data-Driven Coupling Approach for Prediction of Long-term Cryogenic Propellent Tank Behaviors Combining CFD and Nodal Modeling Techniques

Modeling and simulation of cryogenic propellant tank pressurization in normal gravity

Four-sensor droplet-capable conductivity probe in annular and wispy-annular flows

Investigation of nucleate boiling and bubble dynamics at multiple nucleation sites in subcooled boiling flow

Advanced Instrumentation and Modeling Framework for Two-Phase Flow

Experiment and Modeling of Interfacial Area Concentration of Liquid Film in Upward Annular Two-Phase Flow

Scaling of the Sodium Cartridge Loop in Versatile Test Reactor Using Water Experiments

Mamoru Ishii Information

University

Position

Distinguished Professor of Nuclear Engineering in

Citations(all)

34125

Citations(since 2020)

10148

Cited By

27589

hIndex(all)

78

hIndex(since 2020)

45

i10Index(all)

312

i10Index(since 2020)

194

Email

University Profile Page

Purdue University

Google Scholar

View Google Scholar Profile

Mamoru Ishii Skills & Research Interests

Two-phase flow

Nuclear Engineering

Thermal Hydraulics

Safety Analysis

Two-fluid Model Development

Top articles of Mamoru Ishii

Title

Journal

Author(s)

Publication Date

Razvoj i primena dvostruke elektrootporne sonde za merеnjа u strujnim višejaznim sistemima

Procesna tehnika

Jovica R Riznić

Mamoru Ishii

Shripad Revankar

2024/1/29

An Equation-Free Based Data-Driven Coupling Approach for Prediction of Long-term Cryogenic Propellent Tank Behaviors Combining CFD and Nodal Modeling Techniques

arXiv preprint arXiv:2401.08676

Qiyun Cheng

Huihua Yang

Shanbin Shi

Mamoru Ishii

Wei Ji

2024/1/10

Modeling and simulation of cryogenic propellant tank pressurization in normal gravity

Applied Thermal Engineering

Eymon Lan

Shanbin Shi

Wei Ji

Mamoru Ishii

2024/1/10

Four-sensor droplet-capable conductivity probe in annular and wispy-annular flows

Annals of Nuclear Energy

Charie A Tsoukalas

Yang Zhao

Mamoru Ishii

2024/9/1

Investigation of nucleate boiling and bubble dynamics at multiple nucleation sites in subcooled boiling flow

International Journal of Heat and Mass Transfer

Yang Zhao

Yu-Chen Lin

Ke Tang

Mamoru Ishii

John R Buchanan-Jr

2024/2/1

Advanced Instrumentation and Modeling Framework for Two-Phase Flow

Mamoru Ishii

Yang Zhao

Guanyi Wang

Zhuoran Dang

2023/12/2

Experiment and Modeling of Interfacial Area Concentration of Liquid Film in Upward Annular Two-Phase Flow

Nuclear Technology

Guanyi Wang

Mamoru Ishii

2023/12/2

Scaling of the Sodium Cartridge Loop in Versatile Test Reactor Using Water Experiments

Proc. 19th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-19)

Ran Kong

Zhengting Quan

Adam Dix

Seungjin Kim

Mamoru Ishii

...

2022/3/6

Development of a sodium fast reactor cartridge loop testing capability for the versatile test reactor

Nuclear Science and Engineering

Mitchell T Farmer

Matthew Weathered

Darius Lisowski

Nathan Bremer

Dennis Kilsdonk

...

2022/10/6

Pressure drop in 7-pin wire-wrapped rod bundle for the sodium cartridge loop in versatile test reactor

Nuclear Science and Engineering

Zhengting Quan

Adam Dix

Ran Kong

Seungjin Kim

Mamoru Ishii

...

2022

Towards stochastic modeling for two-phase flow interfacial area predictions: A physics-informed reinforcement learning approach

International Journal of Heat and Mass Transfer

Zhuoran Dang

Mamoru Ishii

2022/8/15

Experimental study of bubble size distribution in bubbly and bubbly-to-slug transition flow

International Journal of Multiphase Flow

Muhao Zhang

Guanyi Wang

Liang-ming Pan

Mamoru Ishii

2022/1/1

Experimental investigation on flashing-induced flow instability in a natural circulation scaled-down test facility

Annals of Nuclear Energy

Sipeng Wang

Yu-Chen Lin

Guanyi Wang

Mamoru Ishii

2022/6/15

Experimental study of the effect of pipe size on bubbly to beyond-bubbly flow regime transition

Experimental Thermal and Fluid Science

Zhuoran Dang

Mamoru Ishii

2022/6/1

CFD Simulations of the Versatile Test Reactor Sodium Cartridge Loop and Scaled Water Loop

Proc. 19th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-19)

Zhengting Quan

Ran Kong

Adam Dix

Seungjin Kim

Mamoru Ishii

...

2022/3/6

Progress in two-phase flow modeling: Interfacial area transport

Seungjin Kim

Mamoru Ishii

Ran Kong

Guanyi Wang

2021/3/1

Comprehensive evaluation of two-group interfacial area transport equation and new intergroup transfer model

International Journal of Heat and Mass Transfer

Guanyi Wang

Mamoru Ishii

2021/8/1

Two-phase flow instability induced by flashing in natural circulation systems: An analytical approach

International Journal of Heat and Mass Transfer

Akshay Kumar Khandelwal

Mamoru Ishii

2021/12/1

Two-phase interfacial area characteristics and transport under the transition from subcooled boiling to saturated boiling flows

Applied Thermal Engineering

Zhuoran Dang

Yang Zhao

Guanyi Wang

Jingyu Du

Mamoru Ishii

2021/2/5

Interfacial area transport for bubbly-to-slug transition flows in small diameter pipes

International Journal of Heat and Mass Transfer

Zhuoran Dang

Mamoru Ishii

2021/6/1

See List of Professors in Mamoru Ishii University(Purdue University)