Thermal-Hydraulic Research Laboratory

Department of Nuclear Engineering

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You are here: Home / Current Projects / Subcooled Flow Boiling Experiments

Subcooled Flow Boiling Experiments

Subcooled flow boiling experimental benchmarks in simple geometries are part of an ongoing two-phase flow fundamental research performed at the Thermal-hydraulics laboratory in the Nuclear Engineering Department. State-of-the-art visualization techniques are simultaneously implemented, including:

  • particle tracking velocimetry (PTV),
  • high speed cinematography (HSC), and
  • high speed infrared thermometry (HSIR-T).

The visualization techniques are complemented with “traditional” point measurement probes, such as thermocouples, pressure transducers, and optical probe sensors to study the two-phase flow dynamics in subcooled boiling. The main goal of these benchmarks is to provide qualitative and quantitative information of the vapor or gas bubbles (void) influence on important two-phase flow parameters such as: void influence on the wall-heat transfer, influence on the neighboring liquid turbulence and influence on the drag.

These experiments are required for the improvement and development of CFD and DNS two-phase flow mechanistic models and empirical correlations.

Subcooled Experiments                         Subcooled Experiments

Tagged With: light water reactor

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Thermal-Hydraulic Research Laboratory

Department of Nuclear Engineering                 3380 University Drive East
College Station, TX 77845

ph. 979-845-4109

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