| 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.identifier.issn |
2224-2007 |
|
| dc.identifier.uri |
http://dspace.mist.ac.bd:8080/xmlui/handle/123456789/959 |
|
| 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.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 |
