Thermal-Hydraulic Research Laboratory

Department of Nuclear Engineering

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You are here: Home / Archives for light water reactor

Pressurized Thermal Shock (PTS) Facility: “The Cold Leg Mixing CFD-UQ benchmark”

PTS Facility

The 5th benchmark of CFD applications to Nuclear reactor safety has been approved by CSNI. Its main objective is to go a step further in the application of single-phase CFD to nuclear safety issues with mixing problems possibly in presence of buoyancy effects. The Pressurized Thermal Shock (PTS) … [Read more...]

Tagged With: light water reactor, Validation & Verification Benchmark

The Generic Safety Issue 191

Core Layout/Profile

Our research team, in collaboration with the South Texas Project Nuclear Operating Company (STPNOC), has solved the Generic Safety Issue (GSI) - 191, a problem resulting from a loss of coolant accident in a nuclear reactor, which can cause debris to be generated and potentially impact the … [Read more...]

Tagged With: light water reactor

Experimental Studies of PWR 5×5 Fuel Bundles

Fuel assemblies of pressurized water reactors (PWRs) are constructed from fuel rods and supports to create rod bundles. To support and maintain the lateral spatial gaps of the rods, support grids are positioned at regular intervals in the direction of axial flow. With the presence of the spacer … [Read more...]

Tagged With: light water reactor

Subcooled Flow Boiling Experiments

Subcooled 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, … [Read more...]

Tagged With: light water reactor

Steam Condensation Test Facility

Steam Condensation Facility

The steam-air condensation facility investigates the phenomena of direct contact condensation that occurs when steam comes in direct contact with water creating a violent and complicated exchange of mass and energy. The heat transfer coefficient between the steam and water is calculated, as well as … [Read more...]

Tagged With: light water reactor

Critical Heat Flux Test Facility

CHF Facility

The Critical Heat Flux / Departure from Nucleate Boiling test loop provides a means of evaluating the DNB performance of test geometries representative of commercial pressurized water reactor (PWR) nuclear fuel. The test facility has operated at the Product Engineering Development Laboratory, which … [Read more...]

Tagged With: light water reactor

Contact Us

Thermal-Hydraulic Research Laboratory
Department of Nuclear Engineering
3380 University Drive East
College Station, TX 77845

ph. 979-845-4109

Thermal-Hydraulic Research Laboratory

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

ph. 979-845-4109

Texas A&M University Department of Nuclear Engineering

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