1
|
Fridman E, Nikitin E, Ponomarev A, Di Nora A, Kliem S, Mikityuk K. Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109619] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/13/2022]
|
2
|
Ponomarev A, Mikityuk K, Zhang L, Nikitin E, Fridman E, Álvarez-Velarde F, Romojaro Otero P, Jiménez-Carrascosa A, García-Herranz N, Lindley B, Baker U, Seubert A, Henry R. Superphénix Benchmark Part I: Results of Static Neutronics. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2022. [DOI: 10.1115/1.4051449] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
In the paper, the specification of a new neutronics benchmark for large sodium cooled fast reactor (SFR) core and results of modeling 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 the results of the reference solution. Different core geometries and thermal conditions from the cold “as fabricated” up to full power were considered. The reference Monte Carlo (MC) 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 modeling with seven other solutions using deterministic and MC 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 the evaluation of transient behavior of the core.
Collapse
Affiliation(s)
- Alexander Ponomarev
- Laboratory for Scientific Computing and Modelling, Paul Scherrer Institute (PSI), Forschungsstrasse 111, Villigen PSI 5232, Switzerland
| | - Konstantin Mikityuk
- Laboratory for Scientific Computing and Modelling, Paul Scherrer Institute (PSI), Forschungsstrasse 111, Villigen PSI 5232, Switzerland
| | - Liang Zhang
- Laboratory for Scientific Computing and Modelling, Paul Scherrer Institute (PSI), Forschungsstrasse 111, Villigen PSI 5232, Switzerland
| | - Evgeny Nikitin
- Reactor Safety Division, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, Dresden DE-01328, Germany
| | - Emil Fridman
- Reactor Safety Division, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, Dresden DE-01328, Germany
| | - Francisco Álvarez-Velarde
- Centro de Investigaciones Energéticas, MedioAmbientales y Tecnológicas (CIEMAT) Avda., Complutense, 40, Madrid 28040, Spain
| | - Pablo Romojaro Otero
- Centro de Investigaciones Energéticas, MedioAmbientales y Tecnológicas (CIEMAT)—Currently at SCK·CEN Avda, Complutense, 40, Madrid 28040, Spain
| | - Antonio Jiménez-Carrascosa
- Instituto de Fusion Nuclear, Universidad Politécnica de Madrid (UPM) José Gutiérrez Abascal, 2, Madrid 28006, Spain
| | - Nuria García-Herranz
- Instituto de Fusion Nuclear, Universidad Politécnica de Madrid (UPM) José Gutiérrez Abascal, 2, Madrid 28006, Spain
| | - Ben Lindley
- Department of Engineering Physics, University of Wisconsin-Madison Engineering Research Building, 1500 Engineering Drive, Madison WI 53706
| | - Una Baker
- Department of Engineering, University of Cambridge, Trumpington Street, Cambridge CB2 1PZ, UK
| | - Armin Seubert
- Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Boltzmannstraße 14, Garching bei München 85748, Germany
| | - Romain Henry
- Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Boltzmannstraße 14, Garching bei München 85748, Germany
| |
Collapse
|
3
|
Talamo A, Cao Y, Gohar Y, Valtavirta V, Leppänen J, Sikorin S, Mandzik S, Polazau S, Hryharovich T. Serpent transient analyses of GIACINT geometrical change experiments. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108601] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
|
4
|
Nguyen TDC, Lee H, Lee D. Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.03.005] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
|
5
|
Di Nora V, Fridman E, Nikitin E, Bilodid Y, Mikityuk K. Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: Methodology demonstration. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108183] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
|
6
|
Rydlewicz W, Fridman E, Shwageraus E. MODELLING ASTRID-LIKE SODIUM-COOLED FAST REACTOR WITH SERPENT-DYN3D CODE SEQUENCE. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124702028] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
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.
Collapse
|
7
|
Häkkinen S, Syrjälahti E, Rintala A. Validation of the Serpent 2-HEXTRAN-SMABRE code sequence in a VVER-1000 coolant transient. J NUCL SCI TECHNOL 2020. [DOI: 10.1080/00223131.2020.1773348] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
Affiliation(s)
- Silja Häkkinen
- VTT Technical Research Centre of Finland Ltd, Espoo, Finland
| | | | - Antti Rintala
- VTT Technical Research Centre of Finland Ltd, Espoo, Finland
| |
Collapse
|
10
|
Nikitin E, Fridman E. Extension of the reactor dynamics code DYN3D to SFR applications – Part III: Validation against the initial phase of the Phenix EOL natural convection test. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.017] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
|