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Generalization of the tibere B1 leakage model to the method of characteristics. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109160] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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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.
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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
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Szogradi M. ANALYSIS OF THE OECD/NEA SFR BENCHMARK WITH ANTS REDUCED-ORDER NODAL DIFFUSION SOLVER AND THE SERPENT MONTE CARLO CODE. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124704021] [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
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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