Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software
| dc.contributor.author | Nusrat Jahan Shanta, Shah | |
| dc.contributor.author | Mollah, Abdus Sattar | |
| dc.date.accessioned | 2025-07-07T05:22:50Z | |
| dc.date.available | 2025-07-07T05:22:50Z | |
| dc.date.issued | 2025-06 | |
| dc.description.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 effortsto 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 gaphas 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. | en_US |
| dc.identifier.issn | 2224-2007 | |
| dc.identifier.uri | http://dspace.mist.ac.bd:8080/xmlui/handle/123456789/959 | |
| dc.language.iso | en | en_US |
| dc.publisher | Research and Development Wing, MIST | en_US |
| dc.subject | VVER-1200, Fuel rod, ANSYS, Low carbon energy | en_US |
| dc.title | Structural and Thermal Analysis of Fuel Rod of VVER-1200 Nuclear Reactor Using ANSYS Software | en_US |
| dc.type | Article | en_US |
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