Authors
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran.
Abstract
Evaluating fuel performance in the event of an accident is an important challenge in safety analysis. To this end, several computational codes have been developed to evaluate the performance of the developed fuel rod. These codes examine the phenomena that governing the behaviour of the fuel rod during an accident include sheath phase alteration, zirconium oxidation, creep deformation, and sheath alloy failure. The aim of the present study is to investigate the performance of the VVER-1000 reactor fuel rod during an LOCA accident using FRAPCON-4.0 and FRAPTRAN-1.5 codes. The sample examined is the VVER-1000 reactor fuel rod in the IFA-650.6 test. Comparison of the obtained results with other published theoretical and experimental results confirms the validity of the code in thermo mechanical analysis of VVER fuel rod. In addition, the simulation results showed that the current safety criteria in the design of LOCA safety systems, it is necessary to consider sheath failure as another safety criterion. This is currently being addressed by the German Commission on Safety (RSK) in the analysis of the LOCA incident.
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