Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software

Shah Nusrat Jahan Shanta; Abdus Sattar Mollah

Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software

Authors

Shah Nusrat Jahan Shanta Department of Nuclear Science and Engineering, Military Institute of Science and Technology (MIST), Dhaka-1216, Bangladesh
Abdus Sattar Mollah Department of Nuclear Science and Engineering, Military Institute of Science and Technology (MIST), Dhaka-1216, Bangladesh

Keywords:

VVER-1200, Fuel rod, ANSYS, Low carbon energy

Abstract

This study focuses on analyzing the thermo-mechanical behavior of fuel rods in VVER-1200 nuclear reactors to ensure their safe and efficient operation. Bangladesh plans to operate two VVER-1200 reactors at Rooppur by 2025/2026, aligning with global efforts to shift toward low-carbon energy sources. The analysis, performed using ANSYS software, evaluates key parameters such as deformation, stress, strain, temperature distribution, and heat flux. A detailed geometric model of the UO₂ fuel rod with zirconium alloy cladding and helium gas in the gap has been developed. Thermal distribution simulations under steady-state conditions reveal critical temperature gradients, while structural analysis identifies high-stress regions due to thermal expansion and operational loads.

MIJST, Vol. 13, June 2025 : 65-71

DOI: https://doi.org/10.47981/j.mijst.13(01)2025.510(65-71)

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Published

2025-07-07

How to Cite

Shanta, S. N. J., & Mollah , A. S. (2025). Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software. MIST International Journal of Science and Technology, 13(1), 65–71. Retrieved from https://banglajol.info/index.php/MIJST/article/view/82800