Strategy for Multi-Scale Single-Phase Flow Coupling

Hu, Rui; Thomas, J. W.; Fanning, T. H.

doi:10.2172/1079137

Cited by 9 publications

(13 citation statements)

References 5 publications

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“…The details of the test simulations can be found in Ref. [16]. These preliminary results provided a proof-of-principle of the coupling strategy between the system code and the CFD code, and demonstrated the significance of the coupled multiscale simulation.…”

Section: Multi--scale Code Couplingmentioning

confidence: 69%

“…The general issues of coupling of system code and CFD code have been addressed in a previous NEAMS report [16], including data exchange method, driving mechanism, time synchronization scheme, and the selection of data for exchange. The coupling strategy between the MOOSE-based system analysis code for SFR and CFD code STAR-CCM+ was derived and implemented based on these considerations and the characteristics of each code.…”

Section: Multi--scale Code Couplingmentioning

confidence: 99%

“…It is briefly discussed here, but the details of the coupling strategy and the implementation can be found in Ref. [16]. The developed strategy for the coupling of MOOSE-based system codes and STAR-CCM+ is also applicable to other multi-scale or multi-physics code coupling applications.…”

Section: Multi--scale Code Couplingmentioning

confidence: 99%

“…The coupling strategy between the SFR Module and STAR-CCM+ has been developed and demonstrated in the previous work [16] by a simple test model as a proof-of-principle. In the protected loss of flow transient of a pool type sodium fast reactor, it is expected that the multi-dimension effects in the cold pool and hot pool, and the formation of thermal stratification layers will play an important role in the evolution of the accident.…”

Section: Coupled System and Cfd Code Simulation Of Abtr Plofmentioning

confidence: 99%

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Development of SFR Primary System Simulation Capability for Advanced System Codes

Thomas

Munkhzul

et al. 2014

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EXECUTIVE SUMMARY Under the Reactor Product Line (RPL) of DOE/NE's Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, an SFR System Analysis Module is being developed at Argonne National Laboratory for whole-plant safety analysis. This tool will simulate tightly coupled physical phenomena-including nuclear fission, heat transfer, fluid dynamics, and thermal-mechanical response-in SFR structures, systems, and components. It is based on the MOOSE (Multi-physics Object-Oriented Simulation Environment) framework, which relies upon open-source libraries such as libMesh and PETSc for mesh generation, finite element analysis, and numerical solutions. This development is a coordinated effort along with the development of RELAP-7, which is an advanced safety analysis tool for light-water reactors developed at Idaho National Laboratory. The SFR Module is aimed to model and simulate the SFR systems with much higher fidelity and with well-defined and validated prediction capabilities. It will provide fast-running, modest-fidelity, whole-plant transient analyses capability, which is essential for fast turnaround design scoping and engineering analyses. The SFR System Module is being built based on RELAP-7 and the MOOSE framework. It leverages the common features between LWRs and SFRs (e.g., single-phase flow in a pipe and steam-system modeling for the balance of plant). The existing RELAP-7 physics models and component library are directly available for use in the SFR System Module. On the other hand, the SFR Module effort assists with RELAP-7 development by providing code verification and contributing general physics models and components applicable to all reactor types. Although the MOOSE and RELAP-7 based SFR system analysis module is a relative new effort (less than two years), significant accomplishments have been achieved. A 1-D FEM flow model using a pressure-based formulation with numerical stabilization schemes has been developed for use in incompressible sodium flows. A set of SFR-specific physics models and component has also been developed. The SFR primary system simulation capabilities of the SFR Module have been demonstrated by simulating the early stage of the Protected Loss-Of-Flow (PLOF) accident in the Advanced Burner Test Reactor (ABTR). Both the steady-state and PLOF transient simulation results are compared with the SAS4A/SASSYS-1 simulation results. It is confirmed that major physics phenomena in the primary coolant loop during the transient can be captured by the SFR Module. The SFR Module also emphasizes providing multi-scale multi-physics modeling capabilities by integrating with other higher-fidelity advanced simulation tools. This investigation is important to the integration between the MOOSE-based system code and the high-fidelity and medium-fidelity advanced simulation capabilities developed under the NEAMS RPL. The multi-scale coupling capability has been demonstrated in the coupled SFR Module and STAR-CCM+ code simulation of the ABTR PLOF transient. The importance of the multi-re...

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Section: Multi--scale Code Couplingmentioning

confidence: 69%

Section: Multi--scale Code Couplingmentioning

confidence: 99%

Section: Multi--scale Code Couplingmentioning

confidence: 99%

Section: Coupled System and Cfd Code Simulation Of Abtr Plofmentioning

confidence: 99%

See 2 more Smart Citations

Development of SFR Primary System Simulation Capability for Advanced System Codes

Thomas

Munkhzul

et al. 2014

Self Cite

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show abstract

“…Careful control of data exchange flow and the time-synchronization is essential for a numerically stable and physically valid coupled code simulation. The general issues of coupling of system code and CFD code have been addressed in Hu et al (2013), including data exchange method, driving mechanism, time synchronization scheme, and the selection of data for exchange. The coupling strategy between SAM and STAR-CCM+ was developed and implemented based on these considerations and the characteristics of each code.…”

Section: Tscomparementioning

confidence: 99%

SAM Theory Manual

Hu¹,

Zou²,

Hu³

et al. 2021

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The System Analysis Module (SAM) is an advanced and modern system analysis tool under development at Argonne National Laboratory for advanced non-LWR reactor safety analysis. It aims to provide fast-running, modest-fidelity, whole-plant transient analyses capabilities, which are essential for fast turnaround design scoping and engineering analyses of advanced reactor concepts. While SAM is being developed as a system-level modeling and simulation tool, advanced modeling techniques being implemented include a reduced-order three-dimensional module, pseudo 3-D conjugate heat transfer modeling in reactor core, flexible and multi-scale modeling of heat transfer between fluid and structures, in addition to the advances in software environments and design, and numerical methods.SAM aims to be a generic system-level safety analysis tool for advanced non-LWRs, including Liquid-Metal-cooled fast Reactors (LMR), Molten Salt Reactors (MSR), Fluoride-salt-cooled Hightemperature Reactors (FHR), and High-Temperature Gas-cooled Reactors (HTGR). SAM takes advantage of advances in physical modeling, numerical methods, and software engineering to enhance its user experience and usability. It utilizes an object-oriented computational framework (MOOSE), and its underlying meshing and finite-element library and linear and non-linear solvers, to leverage the modern advanced software environments and numerical methods.This document provides the theoretical and technical basis of the code to help users understand the underlying physical models (such as governing equations, closure models, and component models), system modeling approaches, numerical discretization and solution methods, and the overall capabilities in SAM. As new code capabilities and features are added, the SAM Theory Manual will be updated periodically to keep it consistent with the state of the development.

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