Flux expansion nodal method for solving multigroup neutron diffusion equations in hexagonal-z geometry

Xia, Bangyang; Xie, Zhongliang

doi:10.1016/j.anucene.2005.06.011

Cited by 15 publications

(1 citation statement)

References 7 publications

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“…The development of the Ants reduced-order nodal diffusion solver has started at VTT in 2018 [11,12]. The in-house built code is based on the analytic function expansion nodal (AFEN) -and function expansion nodal methods (FENM) [13,14]. The algorithm tackles the large number of nodal variables without transverse integration which is beneficial considering hexagonal geometry but has a negative impact on solver speed.…”

Section: Code and Input Structurementioning

confidence: 99%

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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Section: Code and Input Structurementioning

confidence: 99%