skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Annular Flow Simulation Supported by Iterative In-Memory Mesh Adaptation

Journal Article · · Nuclear Science and Engineering
ORCiD logo [1];  [2];  [3];  [4]; ORCiD logo [5]; ORCiD logo [2]
  1. Argonne National Lab. (ANL), Lemont, IL (United States)
  2. Univ. of Colorado, Boulder, CO (United States)
  3. Rensselaer Polytechnic Inst., Troy, NY (United States)
  4. Argonne National Lab. (ANL), Lemont, IL (United States). Argonne Leadership Computing Facility (ALCF)
  5. North Carolina State Univ., Raleigh, NC (United States)

Various flow regimes exist in a boiling water reactor (BWR) as the steam quality increases in the uprising coolant flow, from bubbly flow, slug/churn flow, to annular flow. The annular flow is characterized by the presence of a fast-moving gas core and the surrounding liquid film flowing on the conduit wall. Additionally, entrained droplets can be observed in the gas core with ingested bubbles in the liquid film. The dynamics occurring on the wavy interface between the liquid film and gas core plays a crucial role in affecting the heat transfer rate and pressure drop within the BWR core. However, a fundamental understanding of annular flow is still lacking, partly due to the difficulty in obtaining detailed local data in annular flow experiments. In the current study, a novel simulation framework is developed for the annular flow by coupling a computational fluid dynamics flow solver with state-of-the-art meshing software. The gas-liquid interface is tracked with the level set method. Based on the computed flow solutions, the computational mesh is dynamically adapted in memory to meet the local mesh resolution requirement. This iterative simulation-adaptation framework can ensure the fine mesh resolution across the interface, which not only helps mitigate the mass conservation degradation known to level set methods but also improves the representation of dramatic interface topological changes such as wave breaking and droplet entrainment. The present investigation will shed light onto the complex interfacial processes involved in annular flow and generate much needed simulation data for annular flow modeling.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States). Argonne Leadership Computing Facility (ALCF)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1756316
Journal Information:
Nuclear Science and Engineering, Vol. 194, Issue 8-9; Conference: 18.International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Portland, OR (United States), 18-23 Aug 2019; ISSN 0029-5639
Publisher:
American Nuclear Society - Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (22)

Scalable Implicit Flow Solver for Realistic Wing Simulations with Flow Control journal November 2014
The interfacial drag and the height of the wall layer in annular flows journal November 1976
PUMI: Parallel Unstructured Mesh Infrastructure journal May 2016
Detached direct numerical simulations of turbulent two-phase bubbly channel flow journal July 2011
Sub-channel flow regime maps in vertical rod bundles with spacer grids journal July 2018
Two-phase Flow Patterns in a Four by Four Rod Bundle journal June 2007
Hydrodynamic simulation of air bubble implosion using a level set approach journal June 2006
Improving Unstructured Mesh Partitions for Multiple Criteria Using Mesh Adjacencies journal January 2018
Flow regime transition criteria for upward two-phase flow in vertical rod bundles journal May 2017
Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL) journal May 2016
CFD model of diabatic annular two-phase flow using the Eulerian–Lagrangian approach journal March 2015
Interface tracking simulations of bubbly flows in PWR relevant geometries journal February 2017
A continuum method for modeling surface tension journal June 1992
Bubble tracking analysis of PWR two-phase flow simulations based on the level set method journal November 2017
A stabilized finite element method for the incompressible Navier-Stokes equations using a hierarchical basis journal January 2001
Interface Tracking Investigation of Geometric Effects on the Bubbly Flow in PWR Subchannels journal August 2018
In-memory integration of existing software components for parallel adaptive unstructured mesh workflows: In-memory integration of existing software components for parallel adaptive unstructured mesh workflows journal April 2018
Numerical study of three-dimensional droplet impact on a flowing liquid film in annular two-phase flow journal July 2017
Modeling of annular two-phase flow using a unified CFD approach journal July 2016
A parallel adaptive mesh method for the numerical simulation of multiphase flows journal October 2013
An improved level set method for incompressible two-phase flows journal June 1998
Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing journal February 2020

Similar Records

Local Measurement in Annular Flows Using a Two-Sensor Droplet-Capable Conductivity Probe
Journal Article · Fri Jul 01 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1756316

Two-phase Flow Regime Transition Study using Level-Set Method
Journal Article · Fri Jul 01 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1756316

Heat transfer in an upflowing annular-dispersed flow
Conference · Fri Jul 01 00:00:00 EDT 1983 · HTD (Publ.) (Am. Soc. Mech. Eng.); (United States) · OSTI ID:1756316