Abstract
We have developed a new light-weight fuel behavior code
FINIX, specifically designed for modeling of LWR fuel
rods in multiphysics simulations. A thermomechanical
description of the rod is required especially in
transient conditions, where the heat transfer and changes
in the rod's physical dimensions are strongly coupled. In
addition to the mechanical deformations, FINIX solves the
temperature distribution in the rod and the heat flux
from the cladding to the coolant, allowing two-way
coupling of the fuel behavior simulation with both
neutronics and thermal hydraulics simulations. In this
paper, we describe the FINIX module and compare its
performance with experimental data and FRAPTRAN-1.4, a
widely used fuel behavior code. The comparison reveals
good agreement in both cases. We also demonstrate how
FINIX can be integrated into multiphysics simulations.
Coupled with the Monte Carlo reactor physics code
Serpent, we simulate a fast reactivity transient with the
fuel temperature and fission power solved
self-consistently. With the reactor dynamics codes
TRAB-1D and TRAB3D/SMABRE, we simulate a fast power
transient and a PWR main steam line break. The latter
serves as an example of coupled fuel behavior, neutronics
and system-level thermal hydraulics simulation.
Original language | English |
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Pages (from-to) | 111-121 |
Journal | Annals of Nuclear Energy |
Volume | 84 |
DOIs | |
Publication status | Published - 2015 |
MoE publication type | A1 Journal article-refereed |
Keywords
- fuel rod behavior
- nuclear fuel modeling
- multiphysics
- FINIX