Abstract
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium-cooled Fast Reactors (SFRs) with complex core geometries, such as the ASTRIDlike design. The core is characterised by a highly heterogeneous configuration and was likely to challenge the accuracy of the Serpent-DYN3D sequence. It includes axially heterogeneous fuel assemblies, non-uniform fuel assembly heights and large sodium plena. Consequently, the influence of generation and correction methods of various homogenised, few-group crosssections (XS) on the accuracy of the full-core nodal diffusion DYN3D calculations is presented. An attempt to compare the approximate time effort spent on models preparation against the accuracy of the result is made. Results are compared to reference full-core Serpent MC (Monte Carlo) solutions. Initially, XS data was generated in Serpent using traditional methods (2D single assemblies and 2D super-cells). Full core calculations and MC simulations offered a moderate agreement. Therefore, XS generation with 2D fuel-reflector models and 3D single assembly models was verified. Super-homogenisation (SPH) factors for XS correction were applied. In conclusion, the performed work suggests that Serpent-DYN3D sequence could be used for the analysis of highly heterogeneous SFR designs similar to the studied ASTRID-like, with an only small penalty on the accuracy of the core reactivity and radial power distribution prediction. However, the XS generation route would need to include the correction with SPH factors and generation of XS with various MC models, for different core regions. At a certain point, there are diminishing returns to using more complex XS generation methods, as the accuracy of full-core deterministic calculations improves only slightly, while the time effort required increases significantly.
Highlights
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium-cooled Fast Reactors (SFRs) with complex core geometries, such as the ASTRIDlike design
Some recently conducted studies have shown the potential of the Monte Carlo (MC) Serpent code to generate homogenised, few-group cross-sections (XS) for full core nodal diffusion analyses of conventional designs of Sodium-cooled Fast Reactors (SFRs) using the DYN3D package
The goal of this study was to test the feasibility of applying the Serpent-DYN3D sequence to the calculations of an SFR core of a non-standard design - ASTRID-like
Summary
Some recently conducted studies have shown the potential of the Monte Carlo (MC) Serpent code to generate homogenised, few-group cross-sections (XS) for full core nodal diffusion analyses of conventional designs of Sodium-cooled Fast Reactors (SFRs) using the DYN3D package. They indicate that there is merit in applying Serpent MC code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