Research Center for LWR Engineering
Advancing understanding of reactor thermal-hydraulics.
The Thermal Hydraulics Team develops numerical methods, validation experiments, and measurement technologies for two-phase and multiphase flows to support safety enhancement of light water reactors.
Updates
Latest information
April 2026
The detailed thermo-hydraulic analysis code JUPITER has been released as open source.Click here for details
April 2026
The organization has been renamed to “Research Center for LWR Engineering / Research Group for Nuclear and Reactor Engineering / Thermal Hydraulics Team.”
Novemver 2024
“Technology development for validation of a high-fidelity two-phase flow analysis code for advanced reactor design optimization” has been selected for the Nuclear System R&D Project (Fundamental Team Type) by NUCLEAR SAFETY RESEARCH ASSOCIATION.Click here for details
Core Programs
Main research areas
Numerical analysis code development
We develop high-fidelity numerical methods for two-phase and multiphase flows through code platforms such as JUPITER, TPFIT, and ACE-3D.
Numerical analysis code developmentExperimental research and measurement technology development
We conduct thermal-hydraulics experiments for model validation, establish experimental databases to support predictive accuracy, and develop advanced measurement techniques to visualize and quantify complex flow phenomena.
Experimental research and measurement technology developmentUnderstanding phenomena and model development
We investigate the underlying mechanisms of complex thermal-hydraulics phenomena and enhance predictive capability through the development and refinement of physics-based numerical models.
Understanding and model developmentResearch Snapshot
Research highlights
We conduct integrated research combining numerical analysis and advanced diagnostics to capture complex in-reactor thermal-hydraulics phenomena.
