Modeling and Simulations of Thermal-Fluid Phenomena Related to Pressurized Conduction Cooldown in High Temperature Gas Reactor

Vegendla, Prasad; Hu, Rui; Yuan, Hongyong

doi:10.2172/1483960

Cited by 1 publication

(2 citation statements)

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“…In addition, the future work is to build an integrated tool collaborating with Idaho National Laboratory (INL), this effort aims for the development of a computationally efficient capability that attempts to predict flow and heat transfer in the core and plena during the transient events. To achieve this, we plan to integrate 2-D or 3-D coarse-mesh engineering-scale simulation tools like PRONGHORN (for the core) [9] and 1-D system analysis code SAM (for the primary loop and the plant) [10] along with 3-D tools like Nek5000 (for the plena) [4,7].…”

Section: Discussionmentioning

confidence: 99%

“…For safety and licensing purposes, we must analyze the transient response of High Temperature Gas-cooled Reactor (HTGR) to hypothetical accident scenarios including Pressurized Loss of Forced Circulation (PLOFC). The PLOFC is often associated with a loss of offsite electrical power resulting in failure of the blower to force coolant into the core, the reactor is scrammed and structural integrity remains intact such that there is no loss of coolant mass [4]. Decay heat is removed by natural circulation of the helium coolant, which requires that the flow be reversed from forced downward flow to buoyancydriven upward flow.…”

Section: Introductionmentioning

confidence: 99%

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Modeling and Simulations of Deteriorated Turbulent Heat Transfer in Wall Heated Cylindrical Tube

Vegendla

2019

ASME 2019 Verification and Validation Symposium

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The paper discusses the modeling and simulations of Deteriorated Turbulent Heat Transfer (DTHT) for a wall-heated fluid flows, which can be observed in gas-cooled nuclear power reactors during Pressurized Conduction Cooldown (PCC) event due to loss of force circulation flow. The DTHT regime is defined as the deterioration of normal turbulent heat transport due to increase of acceleration and buoyancy forces. The Computational Fluid Dynamics (CFD) tools such as Nek5000 and STAR-CCM+ can help to analyze the DTHT phenomena in reactors for efficient thermal-fluid designs. 3D CFD non-isothermal modeling and simulations were performed in a wall-heated circular tube. The simulation results were verified with two different CFD tools, Nek5000 and STAR-CCM+, and validated with an experimental data. The predicted bulk temperatures were identical in both CFD tools, as expected. Good agreement between simulated results and measured data were obtained for wall temperatures along the tube axis using Nek5000. In STAR-CCM+, the under-predicted wall temperatures were mainly due to higher turbulence in the wall region. In STAR-CCM+, the predicted DTHT was over 48% at outlet when compared to inlet heat transfer values.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%