Extension of the reactor dynamics code DYN3D to SFR applications – Part II: Validation against the Phenix EOL control rod withdrawal tests

Nikitin, E. E.; Fridman, E.

doi:10.1016/j.anucene.2018.05.016

Cited by 16 publications

(2 citation statements)

References 9 publications

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“…This solver is based on the nodal expansion methods and multigroup approximation. Together with the Monte Carlo code SERPENT [3] as a cross section generator, DYN3D proved to be a competent code for static neutronic analyses of SFR cores [13,14]. In this benchmark, the full core solutions were calculated with DYN3D while the homogenized multigroup cross sections were obtained with the SERPENT code and JEFF-3.1.1 nuclear data [4].…”

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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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

View full text Add to dashboard Cite

show abstract

“…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 [1][2][3][4][5][6][7][8]. This paper concerns the feasibility of applying the Serpent-DYN3D sequence to the calculations of SFR cores with more complex geometries.…”

Section: Introductionmentioning

confidence: 99%

Modelling Astrid-Like Sodium-Cooled Fast Reactor With Serpent-Dyn3d Code Sequence

2021

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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.

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Nuclear physics deterministic code

Zhang

2021

Nuclear Power Plant Design and Analysis Codes

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Extension of the reactor dynamics code DYN3D to SFR applications – Part II: Validation against the Phenix EOL control rod withdrawal tests

Cited by 16 publications

References 9 publications

Superphénix Benchmark Part I: Results of Static Neutronics

Superphénix Benchmark Part I: Results of Static Neutronics

Modelling Astrid-Like Sodium-Cooled Fast Reactor With Serpent-Dyn3d Code Sequence

Nuclear physics deterministic code

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