• Neutronic and thermal-hydraulic performance analysis of nanofluids in pressurized water reactor fuel subchannel. 

  Taimoor, Imtiaz (Institute of Nuclear Power Engineering (INPE), BUET, 2023-08-29)

  This research focuses on the utilization of nanofluids as coolants in Pressurized Water Reactors (PWRs). By focusing on two distinct reactor designs, the AP-1000 with its characteristic square array fuel subchannel and the ...
• Efficient computational analyses of boiling water reactor fuel assemblies. 

  SHAMIM HASSAN, MD. (Institute of Nuclear Power Engineering (INPE), BUET, 2023-08-09)

  This research is focused on the development of computationally efficient artificial neural network (ANN) models for the neutronic analysis of accident-tolerant fuel (ATF) candidates in BWR fuel assemblies. Two ATF options: ...
• New data-driven model for estimating the weather-dependent thermodynamic performance of nuclear power plants 

  Azmaeen-Bin-Amir, SK. (Institute of Nuclear Power Engineering (INPE), BUET, 2023-04-30)

  This research developed a new data-driven model to estimate the impact of condenser pressure, a function of the temperature of the tertiary coolant and thus the surrounding weather, on the thermodynamic performance of a ...
• Safe evacuation routing due to emergency scenarios in Rooppur nuclear power plant during a beyond design-basis accident 

  Dipayan Sikder (Institute of Nuclear Power Engineering (INPE), BUET, 2023-05-10)

  In this study, emergency evacuation routing for Rooppur Nuclear Power Plant (RNPP) was studied by combined analysis using Personal Computer Transient Analyzer (PCTran) simulator and ArcGIS software. PCTran VVER 1200 and ...

View more