COMPREHENSIVE ANALYSIS OF THE OECD/NES KALININ-3 BENCHMARK (PHASE 1-3) BY USING ATHLET AND ATHLET/KIKO3D COUPLED CODES

Gyorgy Hegyi, Andras Kereszturi, Istvan Trosztel, Zsolt Elter, Centre for Energy Research Hungarian Academy of Sciences, Hungary

24th Symposium of AER on VVER Reactor Physics and Reactor Safety (2014, Sochi, Russia)
Reactor dynamics and safety analysis

Abstract

COMPREHENSIVE ANALYSIS OF THE OECD/NEA KALININ-3 BENCHMARK (PHASE 1-3) BY USING AHLET AND ATHLET/KIKO3D COUPLED CODES
György Hegyi, András Keresztúri, István Trosztel, Zsolt Elter
Centre for Energy Research Hungarian Academy of Sciences, Budapest, Hungary
gyorgy.HEGYI@energia.mta.hu
ABSTRACT
The reliable prediction of the global and local reactor parameters is important issue to achieve a high validation stage of the coupled neutron-physics/thermal-hydraulics system codes which nowadays are considered to be the state of art by performing of accident analysis. It is similarly important to be able giving an answer and assurance of the following questions:

• how good and correct are the applied models in the simulation tools,
• the accuracy of the numerical methods incorporated in the codes,
• the completeness of the methodology to describe the multi-physical processes,
• the correctness of the required input data to model the processes.
  The paper gives a short summary of the Nuclear Energy Agency (NEA) of the
  Organization for Economic Cooperation and Development (OECD) VVER-1000 (Kalinin-3) ‘Switching-off of one Main Circulation Pump (MCP)’ transient benchmark for evaluating coupled system codes. The large number of available real plant experimental data made these benchmark problems very valuable.
  The experiment is very well documented, its uncertainties are known and the measurements were performed with a quite high frequency.
  In the first exercise instead of the complicate reactor-physical model the ATHLET 2.1 code with its point kinetics method (its parameters given in the benchmark specification) was used. Then in the second exercise, the core and the vessel are modelled. The inlet and outlet core transient boundary conditions and appropriate parameterized cross section data are provided by the benchmark team. In the third phase the full reactor is modelled.
  In the paper, our final solution of the above detailed benchmark problem is presented and the results are compared to documented experimental data.

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