Scaling analysis for the high temperature Gas Reactor Test Section (GRTS)

Reyes, J.N.; Groome, John; Woods, Brian; Jackson, Brian; Marshall, Theron D.

doi:10.1016/j.nucengdes.2009.03.020

Cited by 21 publications

(10 citation statements)

References 2 publications

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“…There is an ongoing study related to P2P natural circulation thermal‐hydraulics behavior is being conducted at OSU. Hence, detailed scaling analysis have been conducted to design and construct the HTTF with reference to the MHTGR . This scaling analysis is based on the hierarchical two‐tired scaling methodology that was described by Zuber et al The analytical solution of this methodology yields design specification of the integral effects HTTF at OSU and the scaling dimensionless parameters that accounts for the degree of mixing in the upper plenum.…”

Section: Resultsmentioning

confidence: 99%

Natural convection inside heated channel of a facility representing prismatic modular reactor core

et al. 2018

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The newly developed Plenum-to-Plenum facility (P2PF) at Missouri S&T has shown to be an innovative separate effects test facility representing the geometry of prismatic modular reactors. Thermal and velocity fields inside this dual channel facility have been investigated under different natural circulation intensities. It is found that temperature and velocity profiles are function of the measurements locations and the amount of heat supplied to the channel. Quantification of the overall Rayleigh number Ra ð Þ versus overall Reynold number Re ð Þ are found to be related by Re a Ra 0:58 . Upper plenum mixing was characterized by determining the modified Reynold number Re m ð Þ and Froude number 1=Fr 2 À Á dimensionless groups. Analysis of these dimensionless groups along with observable turbulence amplifications emphasize relevance of adopting axial temperature inflection as a criterion for initiation of naturally driven flow destabilization inside vertical heated channels. Additionally, quantification of the distortion factors for characteristic dimensionless groups reveal a good similarity between the P2PF and the Modular High Temperature Gas-cooled Reactor.

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Section: Resultsmentioning

confidence: 99%

Natural convection inside heated channel of a facility representing prismatic modular reactor core

et al. 2018

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“…An excellent example of such a facility would the Gas Reactor Test Section (GRTS) [13], which became the High Temperature Test Facility. These integral facilities (usually) implement a form of scaling analysis in order to interrogate transfer rates and then seek to preserve the relative magnitudes of those transfer rates in order to accurately simulate accident progression.…”

Section: Definition and Role Of Integral Effects Test Facilitiesmentioning

confidence: 99%

Fluid Stratification Separate Effects Analysis, Testing and Benchmarking

Graves

Klein

2018

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High Temperature Gas Reactors (HTGRs) are positioned to disrupt local and global markets via their unique ability to produce carbon-free process heat, high efficiency power generation, and passively safe operational features. However, significant impediments still exist to delay deployment of this particular technology, including a lack of experimental data, verified code application, and lack of consensus with regards to severe accident progression. In particular, air ingress accidents represent a particular challenge to designers and engineers, as they represent low probability, but highly complex, accident scenarios. Including phenomena such as molecular diffusion, free convection, and complex heat and mass transfer paths, experimental and traceable data is essential to maturing the state of the industry. Therefore, this work presents an experimental investigation of the transition to natural convection in HTGR applications using the Stratified Flow Separate Effects Test Facility, housed at Oregon State University. In particular, this work will present data that challenges the assumption that molecular diffusion is a significant factor in this severe accident in the reference facility of the General Atomic 600 MWth Gas Turbine-Modular Helium Reactor (GT-MHR). Rather, experimentally produced data shows a statistically suggestive retardant effect of cross duct orientation, indicating that ingress mechanics may be fundamentally altered via facility geometry. Experimentally, this is achieved using a simplified cross duct that may be positioned in one of two ways so as to provide either horizontal or vertical access to the lower plenum area. Onset of natural convection (ONC) is measured using an oxygen sensor probe, immersed in the helium working fluid, so as to provide direct indication of air presence in the upper plenum. This document will present the doctoral dissertation produced by this work, along with its analysis, experimental data, observations, and conclusions, in addition to select documents that will highlight critical changes during the development process. Those documents will include the quality assurance plan, all subsequent change requests, and the engineering transfer from Harris Thermal in order to establish the most complete quality record possible.

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“…This graphite test section was 2.78 m long and had a flow channel of 16.8 mm diameter along the central axis through which compressed gas flowed upward. The coolant channel radius was chosen based on previous studies [28][29][30][31]. The graphite test section also contained four 12.7 mm diameter holes symmetrically placed around the coolant channel for insertion of electric heater rods (D heater ¼ 12.7 mm) as shown in Fig.…”

Section: Test Section Design and Open-loop System Formentioning

confidence: 99%

Experimental Investigation of Convection Heat Transfer in High Pressure and High Temperature Gas Flows

Valentin

Anderson

Kawaji

2017

Journal of Heat Transfer

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This work focuses on an experimental investigation of convection heat transfer to a gas in a vertical tube under strongly heated conditions at high temperatures and pressures up to 943 K and 65 bar. A unique test facility for convection heat transfer experiments has been constructed, and used to obtain experimental data useful for better understanding and validation of numerical simulation models. This test facility consists of a single flow channel in a 2.7 m long, 0.11 m diameter graphite column with four 2.3 kW heaters placed symmetrically around the 16.8 mm diameter flow channel. Upward flow convection experiments with air and nitrogen were conducted for inlet Reynolds numbers from 1300 to 60,000, thus covering laminar, transition, and fully turbulent flow regimes. Experiments were performed at different flow rates (3.8 Â 10 À4 to 1.5 Â 10 À2 kg/s) and heater power up to 6 kW. Importantly, the data analysis considered the thermophysical properties of the gas and graphite changing with temperature and pressure. Nusselt number results are further compared to existing correlations. The effect of pressure and heater power on degraded heat transfer is examined. The analyses of the experimental data showed significant reductions in Reynolds number of up to 50% and Nusselt numbers of up to 90% between the gas inlet and outlet.

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Scaling analysis for the high temperature Gas Reactor Test Section (GRTS)

Cited by 21 publications

References 2 publications

Natural convection inside heated channel of a facility representing prismatic modular reactor core

Natural convection inside heated channel of a facility representing prismatic modular reactor core

Fluid Stratification Separate Effects Analysis, Testing and Benchmarking

Experimental Investigation of Convection Heat Transfer in High Pressure and High Temperature Gas Flows

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