VTT TECHNICAL RESEARCH CENTRE OF FINLAND...
Transcript of VTT TECHNICAL RESEARCH CENTRE OF FINLAND...
NuFOAM: OpenFOAM in
nuclear safety applications Juho Peltola1 • Juhaveikko Ala-Juusela2 • Tomas Brockmann2 • Karoliina Ekström3 • Jarto Niemi1 • Giteshkumar
Patel4 • Timo Pättikangas1 • Timo Siikonen2 • Vesa Tanskanen4 • Timo Toppila3
1VTT Technical Research Centre of Finland • 2Aalto University • 3Fortum Power and Heat Oy • 4Lappeenranta
University of Technology
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CEA DEBORA5 Experiment R-12 boiling in a vertical pipe
Two-phase solver development The OpenFOAM® based two-fluid CFD solver has been
capabilities have been extended to modeling of subcooled
nucleate boiling, along with several other enhancements. The
results have been benchmarked against experimental and
numerical results. Direct contact condensation (DCC) models
have been implemented and first test simulations of steam
condensation in a water pool have been carried out.
A C E
Frank et al. (2011)
OECD/NEA PSBT 1.2211 Benchmark case A steady-state PWR subchannel experiment
OpenFOAM® and OpenCFD® are registered trademarks of OpenCFD Ltd. (ESI Group)
and this project has not been endorsed or approved by OpenCFD Ltd.
Introduction Compared to commercial solvers, the benefits of an open source
CFD code are transparency, infinite customizability and lack of
licensing fees, which brings the cost structure of massively
parallel computation down to a feasible level. Compared to other
open source CFD codes, the benefits of OpenFOAM® are a large,
active and growing user base, modern approach to mesh handling
with unstructured and polyhedral meshes, parallelization and an
object oriented code structure that makes it fast and easy to
implement new models and solvers in the top level code.
Single-phase flow simulations Fortum took part in the MATIS-H benchmark, simulating a
horizontal fuel rod bundle with a spacer grid utilizing RANS
turbulence modeling. The main emphasis of Aalto University has
been on the VVER-440 fuel rod bundle with different turbulence
modeling approaches, including Large-Eddy Simulation (LES) and
Detached-Eddy Simulation (DES).
OECD/NRC MATIS-H Benchmark Single-phase horizontal fuel rod bundle with a spacer grid. The
Fortum submission was selected as the best k-ε approximation of
the experiment.
VVER-440 fuel rod bundle simulations
1 cm above the spacer grid
k-ε k-ω SST RSTM
a) c)
b) d)
a) 1 cm
b) 2 cm
c) 5 cm
d) 20 cm
above the
spacer grid