The LIFT lab currently houses three separate facilities: the Endurance Flow Loop, Laser-Imaged Natural Circulation Facility, and the Camera-Observed and Instrumented Loop Facility.
The Global Threat Reduction Initiative (GTRI) is a National Nuclear Security Administration (NNSA) nonproliferation program which aims to convert research reactors from the use of highly enriched uranium (HEU) to low enriched Uranium (LEU). Oregon State University is contracted by the Idaho National Laboratory to aid in the qualification of an ultra-high density Uranium-Molybdenum fuel for use in these reactors. As part of this project, the Endurance Flow Loop will study the long-term effects of the in-pile conditions on the fuel elements over the cycle length of the reactor, which is about one year
The Endurance Flow Loop (EFL) is a parallel system welded stainless steel flow loop designed to force a controlled volumetric rate of water over mock-up reactor fuel plates to simulate in-pile hydraulic conditions. Although compact in size, the EFL is outfitted with a number of different flow paths balanced by strategically placed valves to divert flow in the necessary manner to achieve desired flow and pressure conditions over the fuel elements. All hardware and sensors on the EFL are controlled or monitored through a Data Acquisition System (DAS) and displayed in a Graphical User Interface (GUI) control panel on the computer.
The driving force for the flow in the EFL is the twin-stage 10-hp vertical in-line pump that can deliver 35-225 GPM and can provide a differential pressure of up to 200 ft. dynamic head. This pump is controlled via a Variable Speed Drive (VSD) which adjusts the rotational speed of the pump. Flow through the EFL is measured from three vortex-style Rosemount flowmeters, which cover the whole operational range of the system. Pressure transmitters are placed around the facility to monitor the gage pressure of the inlet test sections, and the differential pressure across the fuel elements, and across the pump. Three thermocouples are located on the facility to measure the bulk coolant temperature and the differential temperature across the pump. Water quality is measured from the PH and Conductivity probes.
The Laser-Imaged Natural Circulation (LINC) Facility is an experimental apparatus designed for the observation of natural circulation phenomena associated with vertical, heated cylinders. Continuous operation of natural circulation flow is made possible by a cooling plate that makes up the top of an acrylic tank, designed to allow heater rods to pass through in configurations that include two 3/8” rods with variable pitch or one rod with variable diameter. It leverages Particle Image Velocimetry (PIV) as well as an array of thermocouples to measure heat transfer and time-resolved fluid velocity. From these measurements, deductions can be made about boundary layer thickness, heat transfer rate, boundary layer transition location, time-resolved velocity profiles and more.
The purpose of the LINC Facility is to provide valuable data in support of furthering understanding natural convection in this geometry. It is of particular interest to the nuclear engineering field as the majority of nuclear fuel in use in the world consists of long, slender cylinders which are immersed in water and cooled via natural convection for much of its life. The data acquired from the LINC facility can be applied directly to safety and performance assessment models used to maintain nuclear fuel at safe temperatures at all times.
The LINC Facility allows for investigations using two rod configurations with variable pitch as well as one-rod configurations with variable rod diameter. The maximum power that can be supplied to each rod (and removed by the cooling plate) is 1,400 W, powered by a digital power supply with feedback of actual power used. Velocity field data can be collected using the PIV system at frequencies of 5,000 Hz. Temperature is monitored at many locations including inside the tank, internal to the heater rod(s) and at the inlet and outlet of the cooling plate. The chiller that circulates coolant through the cooling plate has a rating of 1,700 W at 20°C. The tank operates at atmospheric pressure.
The Camera-Observed and Instrumented Loop (COIL) Facility uses a high speed camera and pressure transducers to analyze cross-flow induced vibrations of a test element over a range of flow regimes. A clear glass cylinder allows for visual access to the element under analysis and an angled mirror provides a simultaneous second view for three-dimensional reconstruction. The initial test element is an aluminum wire wound into a helical coil and attached to an inner cylinder. Piping connects the test section to a fluid reservoir with flow provided by a circulating pump. Flow control meters provide manual control of flow rate. Pressure transducers, before and after the test section, meter gauge and differential pressure across the helical coil.
The purpose of this facility is to fully characterize the motion of a helical coil over a range of flow rates. This will provide insight into how steady flow affects flexible structural elements under similar conditions. A similar geometry is found in current integral Pressurized Water Reactor (iPWR) steam generators. It will also provide empirical data on the pressure drop across a coil under fluid flow when suspended in an annulus.
Flow in this facility has a range between 0.4 and 14 gpm with a fine adjustment resolution of 0.2 gpm. Internal gauge pressure in the test section varies based on the flow conditions, ranging from 0.0 to 12 psig. Pressure drop across the test section can be detected with 0.015 psig accuracy. Adjustment of camera placement gives a range of pixel resolution, from 0.002 to 0.006 inches per pixel.