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2 PublicationsDynamic modeling of the neutronic behavior of pressure wave propagation in the Phenix reactor core by using nodal diffusion code DYN3D
This paper presents a methodology for time-dependent neutronic analysis of non-uniform deformations
in Sodium Fast Reactor (SFR) cores using the coordinate transformation method. The
methodology was developed for the 3D nodal diffusion code DYN3D, which uses a regular nodal
mesh for its neutronic solvers. To test the methodology, static and dynamic reactivity variations
induced by a postulated pressure spike in the Phenix reactor leading to dynamic core deformation
were calculated with DYN3D. The time-dependent mechanical core deformations were evaluated
beforehand and provided to this study as CAD geometry snapshots. The validity of the method
was demonstrated by comparing the DYN3D results against a Monte Carlo reference solution.
Static reference calculations were carried out beforehand using the Monte Carlo code Serpent,
with CAD snapshots directly used as geometry inputs. The study achieved a very good agreement
between diffusion calculations using coordinate transformation and the MC calculations using
deformed CAD geometries.
Keywords: SFR; thermal expansion; core deformation; nodal diffusion; DYN3D
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Contribution to proceedings
The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 13.-17.08.2023, Niagara Falls, Ontario, Canada -
Lecture (Conference)
2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2023, 13.-17.08.2023, Niagara Falls, Canada
Permalink: https://www.hzdr.de/publications/Publ-37014