Authors & Affiliations
Bosquet J.1, Velkov K.1, Pasychnyk I.1, Seubert A.1, Danicheva I.A.2, Khrennikov N.N.2, Samokhin A.G.2, Ivanov V.S.2, Kliem S. 3
1Gesellschaft fьr Anlagen- und Reaktorsicherheit, Mьnchen, Germany
2Scientific and Engineering Centre for Nuclear and Radiation Safety, Moscow, Russia
3Helmholtz-Zentrum Dresden Rossendorf, Dresden, Germany
Bosquet J. – PhD, Researcher, Gesellschaft fьr Anlagen- und Reaktorsicherheit.
Velkov K. – PhD, Head of Department, Gesellschaft fьr Anlagen- und Reaktorsicherheit.
Pasychnyk I. – PhD, Researcher, Gesellschaft fьr Anlagen- und Reaktorsicherheit.
Seubert A. – PhD, Researcher, Gesellschaft fьr Anlagen- und Reaktorsicherheit.
Danicheva I.A. – Head of the laboratory, Scientific and Engineering Centre for Nuclear and Radiation Safety.
Khrennikov N.N. – Cand. Sci. (Phys.-Math.), Deputy Head of Department, Scientific and Engineering Centre for Nuclear and Radiation Safety.
Ivanov V.S. – Engineer, Scientific and Engineering Centre for Nuclear and Radiation Safety.
Kliem S. – PhD, head of department, Helmholtz-Zentrum Dresden Rossendorf.
Gen VI reactor systems are mainly fast reactor systems. In order to study important safety related parameters in NPPs with a fast neutron core the coupled code system ATHLET/DYN3D-MG was developed.
The thermal-hydraulic system code ATHLET is developed in GRS and is very good validated for light water reactors (LWR). In 2014 it was certified in Rostechnadzor for WWER reactors. The released Version ATHLET-3.0, which have not been certified yet, contains all additional developments to describe the thermal-hydraulics in a liquid metal core. The main characteristics of thermo-hydraulic models are presented in this article (liquid metal properties, heat transfer coefficients etc. for lead and sodium coolants). ATHLET 3.0 has already been tested for liquid metal fast neutron systems.
The neutron-physics code DYN3D developed in HZDR is a 3D core model which is very good vali-dated for LWRs. Its multi-neutron group version DYN3D-MG is a diffusion solver with some additions which allow simulation of steady state and transient processes in systems with fast neutron spectrum. To generate the XS-data different lattice codes could be applied (SCALE, HELIOS, SERPENT, etc.) and the XS-libraries can be easy transformed in the well-known NEMTAB format. Specialists of SEC NRS have prepared 28 group XS-library based on SCALE code. This library was verified for liquid metal fast neutron systems on BFS (IPPE) benchmark-experiments.
The verification process of the coupled code system ATHLET/DYN3D-MG has been started and it is based on test calculations for a medium size metallic uranium core. The description of the test was taken from a collection of benchmarks, which was suggested by CEA in working group or reactor physics (WGRP) on sodium fast neutron reactors OECD. The first verification results presented in this article give plausible results for the system behavior which is a good proof of the correct interface (internal coupling) of the two codes. It is plan in the future to validate the coupled code system ATHLET/DYN3D-MG on code–to-code comparisons and on real measurements from experiments and NPPs.
3D modeling, transients, codes, thermohydraulic calculations, coupled codes, verification, fast neutron reactors, liquid metal coolant, sodium coolant, lead coolant
1. Lerchl G., Austregesilo H., Schoffel P., von der Cron D., Weyermann F. Gesellschaft fur Anlagen Und Reaktorsicherheit (GRS). ATHLET Mod 3.0 Cycle A. User's Manual. Nowember 2012.
2. Handbook on Leadbismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermalhydraulics and Technologies. OECD 2007, NEA No. 6195.
3. Gierszewski P., Mikic B., Todreas T. Property Correlations for Lithium, Sodium, Helium, Flibe and Water in Fusion Reactor Applications, Fusion Blanket and Structures Group, MIT, PFC-RR-80-12.
4. Fink J.K., Leibowitz L. Thermodynamic and Transport Properties of Sodium Liquid and Vapor. Argonne National Laboratory, ANL/RE-95/2.
5. Palazzo S., Velkov K., Lerchl G., Van Tichelen K. Analyses of the MYRRHA Spallation Loop with the System Code ATHLET. Annals of Nuclear Energy, 2013, vol. 60, pp. 274-286.
6. Hegyi G., Keresztъri A., Pataki I., Tуta A., Velkov K., Pasichnyk I., Perin Y. Coupling the ATHLET 3.0 and the KIKO3DMG multigroup 3D kinetic code developed for the fast spectrum Gen-IV reactors. Proc. 23rd Int. Conf. Nuclear Energy for New Europe. Portoroz, Slovenia, 2014.
7. Grundman U., Rohde U., Mittag S., Kliem S. DYN3D Code for Calculation of Transience in Light Water Reactors (LWR) with Hexagonal or Quadratic Fuel Elements. Available at: https://www.hzdr.de/FWS/publikat/JB04/JB_04_R16.pdf (accessed 18.11.2016).
8. Fridman E., Shwageraus E. Modeling of SFR cores with Serpent–DYN3D codes sequence. Annals of Nuclear Energy, 2013, vol. 53, pp. 354-363.
9. Bousquet J., Ivanov V. Assessing Reactor Physics Codes Capabilities to Simulate Fast Reactors on the Example of the BN-600 Benchmark. ETSON Award-2015.
10. Kozmenkov Y., Kliem S., Rohde U. Validation and Verification of the Coupled Neutron Kinetic/Thermal Hydraulic System Code DYN3D/ATHLET. Annals of Nuclear Energy, 2015, vol. 84, pp.153-165.
11. Blanchet D., Buiron L., Stauff N., Kim T., Taiwo T. Sodium Fast Reactor Core Definitions (version 1.2). AEN – WPRS Meeting, OECD/NEA 2011.