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Added subchannel release date note
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modules/doc/content/applications/thermal_hydraulics.md

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@@ -14,7 +14,7 @@ The following table summarizes the MOOSE modules providing thermal hydraulics ca
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| Module | Scale | Flow-Formulation | Dimension | Typical Element Count | Typical Runtime | Typical Simulations |
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| :---------------------------------------------------------------------- | :------------------------------------- | :----------------------------------------------------------------------------------------------------------------------------------------------------------- | :----------------------------------------------------------------- | :-------------------- | :-------------- | :----------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- |
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| [Navier-Stokes](navier_stokes/index.md) | Coarse-Mesh CFD \\ \\ RANS simulations | Incompressible, Weakly-Compressible, or Fully-Compressible\\ \\ Single- or Multi-Phase \\ \\ Single- or Multi-Component Flow | Typically, 2D, 2D axisymmetric, or 3D \\ \\ Can also be used in 1D | 10,000 | 1 minute | Flow through nuclear reactor core or plena \\ \\ 3D multi-phase flow in pipes \\ \\ Natural convection flow in open cavities |
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| [Subchannel](https://subchannel-dev.hpc.inl.gov/site/index.html) | Subchannel Scale | Incompressible or Weakly-Compressible \\ \\ Single-Phase \\ \\ Single- or Multi-Component Flow | 3D | 100,000 | 10 seconds | Flow development through nuclear reactor fuel assembly \\ \\ Thermal hydraulics analysis of nuclear reactor assembly blockage \\ \\ Natural convection cooling in nuclear reactors low-flow assemblies |
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| [Subchannel](https://subchannel-dev.hpc.inl.gov/site/index.html) (To be released in 2024) | Subchannel Scale | Incompressible or Weakly-Compressible \\ \\ Single-Phase \\ \\ Single- or Multi-Component Flow | 3D | 100,000 | 10 seconds | Flow development through nuclear reactor fuel assembly \\ \\ Thermal hydraulics analysis of nuclear reactor assembly blockage \\ \\ Natural convection cooling in nuclear reactors low-flow assemblies |
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| [Thermal Hydraulics](modules/thermal_hydraulics/index.md) | Lumped-Parameters Simulations | Compressible \\ \\ Single-Phase; Single-Component Flow | 1D, 0D | 100 | 10 seconds | Heat extraction unit from nuclear reactor core \\ \\ Thermal loops with significant compressibility effects |
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| [Porous Flow Module](modules/porous_flow/index.md) | Coarse-Mesh CFD | Incompressible, Weakly-Compressible, or Fully-Compressible Porous Flow (no inertial term) \\ \\ Single- or Multi-Phase \\ \\ Single- or Multi-Component Flow | Typically, 2D, 2D axisymmetric, or 3D \\ \\ Can also be used in 1D | 10,000 | 1 minute | Flow through fractured porous media \\ \\ Underground coal mining \\ \\ CO storage in saline aquifers |
2020

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