|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|NEA-1901/01||Linux-based PC,PC Windows||PC Windows|
FINIX is a fuel behavior module that calculates the thermal and mechanical behavior of a nuclear fuel rod during steady-state and transient conditions. The temperature distribution in the fuel and cladding are solved coupled to the the mechanical behavior of the pellet and cladding as well as the fuel rod internal pressure and fission gas release. Publicly available experimental correlations are used for the material properties, and simple models for the heat transfer from the cladding to the coolant have been included. The scope of the FINIX code is somewhere between the full-fledged fuel performance codes and the simple thermal element: although FINIX employs many of the same experimental correlations as the full fuel performance codes, and solves the thermal and mechanical behavior of the rod, several simplifications have been made, both to improve the performance of the code, and to expedite its development.
The intended use is the improvement of fuel behavior description in neutronics, thermal hydraulics and reactor dynamics codes, without having to employ full-scale fuel performance codes. FINIX couples with the host code on a source code level, and provides an interface of functions that can be used to access the fuel behavior model from the host code. FINIX can also be used stand-alone with input files.
Each FINIX licence is valid for 5 years from the previous release.
User’s may participate in a FINIX discussion forum. More information and advice on the use of FINIX can be obtained by email from email@example.com.
FINIX contains transient and steady-state heat equation solvers. Fuel pellet is considered as a rigid body, and cladding is considered as viscoplastic. Pellet thermal expansion, densification and swelling are modeled. Cladding thermal expansion, elasticity, plasticity and creep are modeled. Fission gas release and radial power distribution are modeled.
Base irradiation can be taken into account alternatively by a FRAPCON restart file or by a FINIX calculation.
|Package ID||Status date||Status|
T. Ikonen, E. Syrjälahti, V. Valtavirta, H. Loukusa, J. Leppänen, and V. Tulkki:
Multiphysics simulation of fast transients with the FINIX fuel behaviour module. EPJ Nuclear Sciences & Technologies, 2:37, 2016.
T. Ikonen, H. Loukusa, E. Syrjälahti, V. Valtavirta, J. Leppänen, and V. Tulkki::
Module for thermomechanical modeling of LWR fuel in multiphysics simulations. Annals of Nuclear Energy, 84:111–121, 2015.
|Package ID||Computer language|
VTT Technical Research Centre of Finland Ltd.
P.O. Box 1000
Keywords: fission gas release, fuel performance, fuel rods, heat generation density profile, heat transfer, mechanical properties, power distribution, steady-state conditions, temperature distribution, thermal expansion, transient analysis.