NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES

This paper presents an assessment of three deterministic core simulators with the focus on the neutronic performance in steady-state calculations of small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and the novel multi-physics solver GeN-Foam. By using these codes, the mult...

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Main Authors: Nikitin E., Fridman E., Mikityuk K., Radman S., Fiorina C.
Format: Article
Language:English
Published: EDP Sciences 2021-01-01
Series:EPJ Web of Conferences
Subjects:
sfr
Online Access:https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10017.pdf
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spelling doaj-924ef8bc19e746afa39dd010555b7fd22021-08-02T23:21:00ZengEDP SciencesEPJ Web of Conferences2100-014X2021-01-012471001710.1051/epjconf/202124710017epjconf_physor2020_10017NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODESNikitin E.0Fridman E.1Mikityuk K.2Radman S.3Fiorina C.4Helmholtz-Zentrum Dresden-Rossendorf (HZDR)Helmholtz-Zentrum Dresden-Rossendorf (HZDR)Paul Scherrer Institute (PSI)École Polytechnique Fédérale de Lausanne (EPFL)École Polytechnique Fédérale de Lausanne (EPFL)This paper presents an assessment of three deterministic core simulators with the focus on the neutronic performance in steady-state calculations of small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and the novel multi-physics solver GeN-Foam. By using these codes, the multi-group diffusion solutions are obtained for the selected twenty control rod worth measurements performed during the isothermal physics tests of the Fast Flux Test Facility (FFTF). The identical set of homogenized few-group cross sections applied in the calculations is generated with the Serpent Monte Carlo code. The numerical results are compared with each other as well as with the measured values. The obtained numerical results, such as the multiplication factors and control rod worth values, are in good agreement as compared to the experimental data. Furthermore, a comparison of the radial power distributions is presented between DYN3D, PARCS and GeN-Foam. Ultimately, the power distributions are compared to the full core Serpent solution, demonstrating an adequate performance of the selected deterministic tools. In overall, this study presents a verification and validation of the neutronic solvers applied by DYN3D, PARCS and GeN-Foam to steady-state calculations of SFR cores.https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10017.pdfsfrdyn3dparcsgen-foamdiffusion solver
collection DOAJ
language English
format Article
sources DOAJ
author Nikitin E.
Fridman E.
Mikityuk K.
Radman S.
Fiorina C.
spellingShingle Nikitin E.
Fridman E.
Mikityuk K.
Radman S.
Fiorina C.
NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
EPJ Web of Conferences
sfr
dyn3d
parcs
gen-foam
diffusion solver
author_facet Nikitin E.
Fridman E.
Mikityuk K.
Radman S.
Fiorina C.
author_sort Nikitin E.
title NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
title_short NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
title_full NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
title_fullStr NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
title_full_unstemmed NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES
title_sort neutronic modelling of the fftf control rod worth measurements with diffusion codes
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2021-01-01
description This paper presents an assessment of three deterministic core simulators with the focus on the neutronic performance in steady-state calculations of small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and the novel multi-physics solver GeN-Foam. By using these codes, the multi-group diffusion solutions are obtained for the selected twenty control rod worth measurements performed during the isothermal physics tests of the Fast Flux Test Facility (FFTF). The identical set of homogenized few-group cross sections applied in the calculations is generated with the Serpent Monte Carlo code. The numerical results are compared with each other as well as with the measured values. The obtained numerical results, such as the multiplication factors and control rod worth values, are in good agreement as compared to the experimental data. Furthermore, a comparison of the radial power distributions is presented between DYN3D, PARCS and GeN-Foam. Ultimately, the power distributions are compared to the full core Serpent solution, demonstrating an adequate performance of the selected deterministic tools. In overall, this study presents a verification and validation of the neutronic solvers applied by DYN3D, PARCS and GeN-Foam to steady-state calculations of SFR cores.
topic sfr
dyn3d
parcs
gen-foam
diffusion solver
url https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10017.pdf
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AT fridmane neutronicmodellingofthefftfcontrolrodworthmeasurementswithdiffusioncodes
AT mikityukk neutronicmodellingofthefftfcontrolrodworthmeasurementswithdiffusioncodes
AT radmans neutronicmodellingofthefftfcontrolrodworthmeasurementswithdiffusioncodes
AT fiorinac neutronicmodellingofthefftfcontrolrodworthmeasurementswithdiffusioncodes
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