SOPHIA: Development of Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications

Jo, Young Beom; Choi, Hae Yoon; Jung, Hyun Woo; Kim, Yun Jae; Kim, Eung Soo

doi:10.1016/j.anucene.2018.09.005

Cited by 24 publications

(5 citation statements)

References 54 publications

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“…The improved MARS-KS model from this study will be used to develop a new integrated analysis framework for in-vessel melt retention. That is, the MARS-KS model for ex-vessel cooling will be coupled with the smoothedparticle hydrodynamics (SPH) code developed by Seoul National University, named SOPHIA [29], which can simulate the behavior of the molten core inside the lower head based on the first principle. In the new analysis tool, the heat flux data from the molten core to the coolant calculated by…”

Section: Discussionmentioning

confidence: 99%

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code

Lee

Park

2023

International Journal of Energy Research

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The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in-vessel melt retention, one requires high-fidelity predictions on the natural circulation flow around the reactor vessel and, in particular, the corresponding critical heat flux (CHF) on a hemispherical lower head. In this study, the coolability limit of external reactor vessel cooling in the Korean APR1400 reactor was investigated numerically by improving a thermal-hydraulic system analysis code, MARS-KS1.5. Since such system analysis codes did not incorporate a CHF model for a downward-facing hemisphere, three CHF correlations were newly implemented in the MARS-KS code, two of them taking into account the effect of the mass flux. A transient analysis on the CHF and surface heat flux on the lower head was carried out while the surrounding cooling water was heated to create the two-phase natural circulation flow. The heat transfer mode on the heated surface was used as a measure of evaluating the success of the strategy, and the simulation results were compared with those obtained via the default CHF model in the code. The sensitivity analysis on the heat load from the core melt was also performed.

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Section: Discussionmentioning

confidence: 99%

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code

Lee

Park

2023

International Journal of Energy Research

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“…As a result, they established a forum and network for programmers as users. However, meshless CFD algorithms based on Lagrangians have recently been created and are being employed in nuclear thermal hydraulics and safety applications [ 86 ]. Turbulent and multi-phase flows and heat transfer models developed based on the conservation equation are now included in the SOPHIA code.…”

Section: Analysis Of Thermal Hydraulics Activities Performed On Hlm-c...mentioning

confidence: 99%

Liquid metal cooled fast reactor thermal hydraulic research development: A review

Agbevanu

Arthur

Debrah

2023

Heliyon

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“…L and R indicate the left and right region of the domain. The reference density and speed of sound are chosen to be 𝜌 0 = 1000 kg∕m 3 and c 0 = 1466 m∕s. The shock tube is taken with the length of 0.1 m and the discontinuity is initially defined at center.…”

Section: Assessment Of Proposed El-wcsph Schemementioning

confidence: 99%

“…Smoothed particle hydrodynamics (SPH) is a Lagrangian‐based meshfree numerical method that traces discretized particles (or parcels) by solving governing equations. This method was first introduced by Lucy 1 and Gingold and Monaghan 2 for solving astrophysics problems, SPH has progressed significantly and has been applied in many other science and engineering fields 3–7 . Owing to its Lagrangian nature, SPH offers intrinsic advantages in handling free surface or multi‐phase flows with large deformations without requiring additional numerical treatment for interface tracking.…”

Section: Introductionmentioning

confidence: 99%

A simple Eulerian–Lagrangian weakly compressible smoothed particle hydrodynamics method for fluid flow and heat transfer

Yoo

Kim

et al. 2022

Numerical Meth Engineering

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In this article, we propose a simple, consistent, and robust Eulerian-Lagrangian weakly compressible smoothed particle hydrodynamics (EL-WCSPH) for the simulation of hydrodynamics and convection heat transfer problems. First, the basic governing equation is formulated using the ALE-SPH framework. The universal formulation is similar to the standard WCSPH, but the degree of Eulerian and Lagrangian schemes can be controlled by inserting a pre-defined arbitrary parameter α ∈ [0, 1]. To alleviate potential numerical errors and inconsistency, particle mass correction is proposed along with particle disorder correction.Then, an algorithm is introduced, in which only a slight modification is necessary compared to the standard WCSPH. Finally, extensive benchmark simulations are conducted to validate the proposed method. As a result, the proposed method is found to perform well in hydrodynamics problems with various flow conditions (pipe flow, lid-driven problem, Taylor-Green vortex, vortex shedding problem, and water sloshing) and thermal-hydraulics problems (natural convection in a square cavity).

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SOPHIA: Development of Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications

Cited by 24 publications

References 54 publications

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code

Liquid metal cooled fast reactor thermal hydraulic research development: A review

A simple Eulerian–Lagrangian weakly compressible smoothed particle hydrodynamics method for fluid flow and heat transfer

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