Superphénix Benchmark Part I: Results of Static Neutronics

Author:

Ponomarev Alexander1,Mikityuk Konstantin1,Zhang Liang1,Nikitin Evgeny2,Fridman Emil2,Álvarez-Velarde Francisco3,Romojaro Otero Pablo4,Jiménez-Carrascosa Antonio5,García-Herranz Nuria5,Lindley Ben6,Baker Una7,Seubert Armin8,Henry Romain8

Affiliation:

1. Laboratory for Scientific Computing and Modelling, Paul Scherrer Institute (PSI), Forschungsstrasse 111, Villigen PSI 5232, Switzerland

2. Reactor Safety Division, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, Dresden DE-01328, Germany

3. Centro de Investigaciones Energéticas, MedioAmbientales y Tecnológicas (CIEMAT) Avda., Complutense, 40, Madrid 28040, Spain

4. Centro de Investigaciones Energéticas, MedioAmbientales y Tecnológicas (CIEMAT)—Currently at SCK·CEN Avda, Complutense, 40, Madrid 28040, Spain

5. Instituto de Fusion Nuclear, Universidad Politécnica de Madrid (UPM) José Gutiérrez Abascal, 2, Madrid 28006, Spain

6. Department of Engineering Physics, University of Wisconsin-Madison Engineering Research Building, 1500 Engineering Drive, Madison WI 53706

7. Department of Engineering, University of Cambridge, Trumpington Street, Cambridge CB2 1PZ, UK

8. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Boltzmannstraße 14, Garching bei München 85748, Germany

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.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference25 articles.

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4. The JEFF-3.1.1 Nuclear Data Library—JEFF Report 22—Validation Results From JEF-2.2 to JEFF-3.1.1,2009

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