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.
Samokhin A.G. – – Junior Researcher, Scientific and Engineering Centre for Nuclear and Radiation Safety. Contacts: 107140, Moscow, Malaya Krasnoselskaya st. 2/8, bld. 5. Tel.: (499) 264-05-96; e-mail:
Ivanov V.S. – Engineer, Scientific and Engineering Centre for Nuclear and Radiation Safety.
Kliem S. – PhD, head of department, Helmholtz-Zentrum Dresden Rossendorf.
Abstract
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.
Keywords
3D modeling, transients, codes, thermohydraulic calculations, coupled codes, verification, fast neutron reactors, liquid metal coolant, sodium coolant, lead coolant
Article Text (PDF, in Russian)
UDC 621.039.526