Measurement of Flow Phenomena in a Lower Plenum Model of a Prismatic Gas-Cooled Reactor

McIlroy, Hugh M.; McEligot, Donald M.; Pink, Robert J.

doi:10.1115/icone16-48734

Cited by 4 publications

(2 citation statements)

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“…Fast transients, such as LOCA's, are not considered. All models are assumed to have the same geometric scaling ratio, S, of 1/6.55, which is chosen to correspond to the scaling ratio employed for the INL isothermal Matched-Index of Refraction (MIR) lower plenum model (McIlroy et al, 2006). The MIR model employs a reduced number of jets (4) and a reduced number of posts (5 plus 10 half-posts at walls) in a geometrically scaled facility to study lower plenum flow.…”

Section: Model Conceptual Design and Scaling Approachmentioning

confidence: 99%

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ICONE15-10808 Scaled Experimental Modeling of VHTR Plenum Flows

McCreery

Condie

Schultz

2007

ICONE

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The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. Various scaled heated and unheated gas and water flow facilities were investigated for modeling VHTR upper and lower plenum flows during the decay heat portion of a pressurized conduction-cooldown scenario and for modeling thermal mixing and stratification ("thermal striping") in the lower plenum during normal operation. It was concluded, based on phenomena scaling and instrumentation and other practical considerations, that a heated water flow scale model facility is preferable to a heated gas flow facility and to unheated facilities which use fluids with ranges of density to simulate the buoyancy effect of heating. For a heated water flow lower plenum model, both the Richardson numbers and Reynolds numbers may be approximately matched for conduction-cooldown natural circulation conditions. Thermal mixing during normal operation may be simulated but at lower, but still fully turbulent, Reynolds numbers than in the prototype. Natural circulation flows in the upper plenum may also be simulated in a separate heated water flow facility that uses the same plumbing as the lower plenum model. However, scaling distortions will occur due primarily to the necessity of using a reduced number of channels connected to the upper plenum than in the prototype in an otherwise geometrically scaled model.Experiments conducted in either or both facilities will meet the objectives of providing benchmark data for the validation of codes proposed for NGNP designs and safety studies, as well as providing a better understanding of the complex flow phenomena in the plenums. Power (NGNP) Project in the U.S., according to MacDonald et al., 2003. The NGNP project has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of a molten-salt coolant is also being evaluated. One of the great challenges of studying, designing, and licensing the NGNP is to verify that the intended NGNP computer code analysis tools can be used with confidence to make decisions and to assure all that the reactor systems are safe and meet their performance objectives. Comparison of computer code calculations with experimental data is the key component of code verification. This paper addresses experimental modeling of lower and upper plenum flow and thermal mixing phenomena of importance during normal operation and during a loss of forced reactor cooling (pressurized conduction cooldown) scenario. A prismatic core gas-cooled reactor following the Gas Turbine-Modular Helium Reactor (GT-MHR) design from General Atomics [GA

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Section: Model Conceptual Design and Scaling Approachmentioning

confidence: 99%

“…The primary measurements of velocities and velocity fluctuations will be performed using a LaVision 3D PIV that is presently being employed for the MIR experiments (McIlroy et al, 2006). The PIV system employs a laser light sheet for illumination.…”

Section: The Japan Society Of Mechanical Engineersmentioning

confidence: 99%