On the use of the SPH method in nodal diffusion analyses of SFR cores

Nikitin, E. E.; Fridman, E.; Mikityuk, Konstantin

doi:10.1016/j.anucene.2015.06.007

Cited by 32 publications

(6 citation statements)

References 9 publications

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“…The maximum difference in total decay heat power estimated by DYN3D and Serpent is less than 0.7%, which is very good agreement considering typical nodal power errors in DYN3D are on the order of 1-3% (Nikitin et al, 2015;Bilodid et al, 2018). Serpent for UOX, MOX and TOX fuels are 6.10%, 5.94% and 5.71%, respectively.…”

Section: Pwr Pin Cell With Uox Mox and Tox Fuelsupporting

confidence: 74%

Explicit decay heat calculation in the nodal diffusion code DYN3D

Bilodid

Fridman

Kotlyar

et al. 2018

Annals of Nuclear Energy

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Section: Pwr Pin Cell With Uox Mox and Tox Fuelsupporting

confidence: 74%

Explicit decay heat calculation in the nodal diffusion code DYN3D

Bilodid

Fridman

Kotlyar

et al. 2018

Annals of Nuclear Energy

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“…Hence the OX system with larger flux gradient on the outer core edge was more sensitive to perturbation from mesh resolution. nodal solution can be significantly improved as reported in [15]. SVR coefficients show larger departure comparing Ants to Serpent, further analysis is required to study the effect of self-shielding in heterogeneous and homogeneous codes.…”

Section: Comparison Of Ants and Serpentmentioning

confidence: 86%

Analysis of the Oecd/Nea SFR Benchmark With Ants Reduced-Order Nodal Diffusion Solver and the Serpent Monte Carlo Code

Szogradi

2021

EPJ Web Conf.

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In order to meet modern industrial and scientific demands the Kraken multi-physics platform’s development was recently launched at VTT Technical Research Centre of Finland. The neutronic solver of the framework consists of two calculation chains, providing full core solutions by the Serpent high fidelity code (1) and the AFEN/FENM-based reduced-order diffusion solver called Ants (2) capable of handling square and hexagonal geometries in steady-state. Present work introduces the simulation of a large 3600 MWth Sodium-cooled Fast Reactor (SFR) described within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of OECD. Full-core 3D results were obtained by Serpent for carbide- and oxide-fuel cores, moreover group constants were generated for Ants utilizing 2D super-cell and single assembly infinite lattice models of Serpent. The continuous-energy Monte Carlo method provided the reference results for the verification of the reduced-order method. Implementing the spatially homogenized properties, 3D solutions were obtained by Ants as well for both core configurations. Comparison was made between the various core designs and codes based on reactivity feedbacks (Doppler constant, sodium voiding, control rod worth) considering power distributions. Regarding reactivity sensitivity on geometry, axial fuel- and radial core expansion coefficients were evaluated as well.

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“…The width of the models was limited to two times the SA pitch. Additionally, the cross sections of CSD, diluent, and empty hexcan structure were corrected with the SPH method [16][17][18].…”

Section: Serpent/dyn3djjef311mentioning

confidence: 99%

Superphénix Benchmark Part I: Results of Static Neutronics

Ponomarev

Mikityuk

Zhang

et al. 2021

Journal of Nuclear Engineering and Radiation Science

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In the paper, the specification of a new neutronics benchmark for a large Sodium cooled Fast Reactor core and results of modelling by different participants are presented. The neutronics benchmark describes the core of the French sodium cooled reactor Superphénix at its startup configuration, which in particular was used for experimental measurement of reactivity characteristics. The benchmark consists of the detailed heterogeneous core specification for neutronic analysis and results of the reference solution. Different core geometries and thermal conditions from cold “as fabricated” up to full power were considered. The reference Monte Carlo solution of Serpent 2 includes data on multiplication factor, power distribution, axial and radial reaction rates distribution, reactivity coefficients and safety characteristics, control rods worth, kinetic data. The results of modelling with seven other solutions using deterministic and Monte Carlo methods are also presented and compared to the reference solution. The comparisons results demonstrate appropriate agreement of evaluated characteristics. The neutronics results will be used in the second phase of the benchmark for evaluation of transient behaviour of the core.

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On the use of the SPH method in nodal diffusion analyses of SFR cores

Cited by 32 publications

References 9 publications

Explicit decay heat calculation in the nodal diffusion code DYN3D

Explicit decay heat calculation in the nodal diffusion code DYN3D

Analysis of the Oecd/Nea SFR Benchmark With Ants Reduced-Order Nodal Diffusion Solver and the Serpent Monte Carlo Code

Superphénix Benchmark Part I: Results of Static Neutronics

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