Computer Programs
NEA-1901 FINIX 0.17.12.
last modified: 06-APR-2018 | catalog | categories | new | search |

NEA-1901 FINIX 0.17.12.

FINIX 0.17.12, thermal and mechanical behaviour of a nuclear fuel rod during steady-state and transient conditions

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1. NAME OR DESIGNATION OF PROGRAM

FINIX v. 0.17.12

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
FINIX 0.17.12 NEA-1901/01 Tested 06-APR-2018

Machines used:

Package ID Orig. computer Test computer
NEA-1901/01 Linux-based PC,PC Windows PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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 finix@vtt.fi.

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4. METHODS

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.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

FINIX is designed for cylindrical geometry. Current version has only been validated with a limited data set, but a thorough validation effort is planned to be done during 2018.

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6. TYPICAL RUNNING TIME

Less than 3 seconds for 100 time steps of base irradiation. Less than 10 seconds for RIA scenario with 3000 time steps. Typical running times are from calculations with typical amounts of radial and axial nodes, e.g. 30 and 10, respectively.

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7. UNUSUAL FEATURES OF THE PROGRAM

FINIX is easily coupled to other programs due to a simple programming interface.

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9. STATUS
Package ID Status date Status
NEA-1901/01 06-APR-2018 Tested restricted
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10. REFERENCES
  • 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.

NEA-1901/01, included references:
- H. Loukusa and V. Valtavirta:
FINIX - Fuel behavior model and interface for multiphysics applications - Code
documentation for version 0.17.12. Technical Report VTT-R-06793-17 (2017)
- H. Loukusa:
Validation of the FINIX fuel behavior code version 0.13.9. Technical Report
VTT-R-06565-13 (2013)
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11. HARDWARE REQUIREMENTS

Windows or UNIX computer.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1901/01 C-LANGUAGE
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13. SOFTWARE REQUIREMENTS

Windows (compiles with msvc, executable provided) or Linux (originally compiles with gcc 4.8.5 on RedHat 64 bit).

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Compiles with Microsoft Visual Studio 2013. Makefile for gcc is included.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Henri Loukusa

VTT Technical Research Centre of Finland Ltd.

P.O. Box 1000

FI-02044 VTT

Finland

finix@vtt.fi

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16. MATERIAL AVAILABLE
NEA-1901/01
Sources
Input files
Output files
Electronic documentation
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • I. Deformation and Stress Distributions, Structural Analysis and Engineering Design Studies

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.