Module for thermomechanical modeling of LWR fuel in multiphysics simulations

Timo Ikonen (Corresponding Author), Henri Loukusa, Elina Syrjälahti, Ville Valtavirta, Jaakko Leppänen, Ville Tulkki

Research output: Contribution to journalArticleScientificpeer-review

7 Citations (Scopus)

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 languageEnglish
Pages (from-to)111-121
JournalAnnals of Nuclear Energy
Volume84
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

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Hydraulics
Steam piping systems
Coolants
Heat flux
Temperature distribution
Physics
Heat transfer
Temperature
Hot Temperature

Keywords

  • fuel rod behavior
  • nuclear fuel modeling
  • multiphysics
  • FINIX

Cite this

@article{254bd4c37695490c837fd25ff7024a96,
title = "Module for thermomechanical modeling of LWR fuel in multiphysics simulations",
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.",
keywords = "fuel rod behavior, nuclear fuel modeling, multiphysics, FINIX",
author = "Timo Ikonen and Henri Loukusa and Elina Syrj{\"a}lahti and Ville Valtavirta and Jaakko Lepp{\"a}nen and Ville Tulkki",
year = "2015",
doi = "10.1016/j.anucene.2014.11.004",
language = "English",
volume = "84",
pages = "111--121",
journal = "Annals of Nuclear Energy",
issn = "0306-4549",
publisher = "Elsevier",

}

Module for thermomechanical modeling of LWR fuel in multiphysics simulations. / Ikonen, Timo (Corresponding Author); Loukusa, Henri; Syrjälahti, Elina; Valtavirta, Ville; Leppänen, Jaakko; Tulkki, Ville.

In: Annals of Nuclear Energy, Vol. 84, 2015, p. 111-121.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Module for thermomechanical modeling of LWR fuel in multiphysics simulations

AU - Ikonen, Timo

AU - Loukusa, Henri

AU - Syrjälahti, Elina

AU - Valtavirta, Ville

AU - Leppänen, Jaakko

AU - Tulkki, Ville

PY - 2015

Y1 - 2015

N2 - 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.

AB - 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.

KW - fuel rod behavior

KW - nuclear fuel modeling

KW - multiphysics

KW - FINIX

U2 - 10.1016/j.anucene.2014.11.004

DO - 10.1016/j.anucene.2014.11.004

M3 - Article

VL - 84

SP - 111

EP - 121

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

ER -