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An integrated coupling model for solving multiscale fluid-fluid coupling problems in SAM code

Journal Article · · Nuclear Engineering and Design
In this study, an integrated coupling method has been developed for solving multiscale fluid-fluid coupling problems in plant-scale safety analysis models in SAM (System Analysis Module) code. In this method, a higher-fidelity multi-dimensional (3D) flow module is used for reactor components of complex flow features (e.g., reactor core) and a lumped parameter one-dimensional (1D) flow module for plant-scale flow loops (e.g., primary loop pipe network), respectively. In this method, the 3D fluid equation/domain and 1D fluid equation/domain are tightly coupled at the residual level and solved simultaneously using the Newton’s method to overcome the convergence issues typically seen in existing approaches like separate domain approach, where the 3D fluid equation and 1D fluid equation are solved separately. Extensive and successful code verifications and demonstrations have been performed for this newly developed method. This new modeling approach significantly simplify the work flow in developing high-fidelity plant-scale safety analysis model, e.g. for pool-type reactors and pebble-bed reactors.
Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS); USNRC
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
2341298
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 404; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (13)

A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation journal March 2001
An integrated relap5-3d and multiphase cfd code system utilizing a semi-implicit coupling technique journal July 2002
System–CFD coupled simulations of flow instability in steam generator U tubes journal August 2014
A novel domain overlapping strategy for the multiscale coupling of CFD with 1D system codes with applications to transient flows journal April 2016
A fully-implicit high-order system thermal-hydraulics model for advanced non-LWR safety analyses journal March 2017
Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors journal May 2017
Coupled system thermal-hydraulic/CFD analysis of a protected loss of flow transient in the MYRRHA reactor journal August 2018
A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phénix Reactor Natural Circulation Test journal October 2014
Comparison of different coupling CFD–STH approaches for pre-test analysis of a TALL-3D experiment journal August 2015
Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project journal August 2015
A novel multi-scale domain overlapping CFD/STH coupling methodology for multi-dimensional flows relevant to nuclear applications journal July 2017
Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses journal April 2019
MOOSE: Enabling massively parallel multiphysics simulation journal January 2020

Figures / Tables (26)


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