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

نویسندگان

چکیده

This paper presents an assessment of three deterministic core simulators with the focus on neutronic performance in steady-state calculations small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and novel multi-physics solver GeN-Foam. By using these codes, multi-group diffusion solutions obtained for twenty control rod worth measurements performed during isothermal physics tests Flux Test Facility (FFTF). identical set homogenized few-group cross sections applied is generated Serpent Monte Carlo code. numerical results compared each other as well measured values. results, such multiplication factors values, good agreement to experimental data. Furthermore, a comparison radial power distributions presented between Ultimately, full solution, demonstrating adequate tools. In overall, this study verification validation solvers by GeN-Foam SFR

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ژورنال

عنوان ژورنال: Epj Web of Conferences

سال: 2021

ISSN: ['2101-6275', '2100-014X']

DOI: https://doi.org/10.1051/epjconf/202124710017