Department of Nuclear Science & Engineering (NSE)

Academic Credentials:

Bachelor of Science in Nuclear Science and Engineering                                    Jan 2016 – Jan 2020

Military Institute of Science and Technology

Bangladesh University of Professionals

CGPA: 3.84/4.00 (1^st position in batch)

Research Experience:

▪ Undergraduate thesis titled:

  “Nuclear Data Processing and Neutronics Analysis of Nuclear Reactors using OpenMC and NJOY21 Codes”

   Thesis supervisor: Prof. Dr. Abdus Sattar Mollah

   Summary: Using the Monte Carlo method, important neutronic parameters and various reaction rates were

   calculated and analyzed for different nuclear reactor configurations. Continuous energy cross-sections were

   processed at multiple specific temperatures for the simulations using nuclear data processing code.

▪ CFD data visualization and analysis using python programming language.

▪ Computational Fluid Dynamics: Droplet dynamics and microfluidics.

▪ Atmospheric dispersion modeling.

Research Articles:

▪ Khan, G. R., Nasim, A. S. M., Erfan, K. A., & Mollah, A. S. (2022). Verification of Monte Carlo Code OpenMC using VVER-1000 MOX Fuel Assembly against Criticality Benchmark Data. In International Journal of Integrated Sciences & Technology 4 S, 7-13. http://www.cuet.ac.bd/IJIST/index.html

▪ Nasim, A. S. M., Khan, G. R., Erfan, K. A., & Mollah, A. S. (2022). Study on processing and validation of ENDF/B-VIII nuclear data library by criticality benchmark of PWR pin cells using NJOY21 and OpenMC. In International Journal of Integrated Sciences & Technology 4 S, 1-6.  http://www.cuet.ac.bd/IJIST/index.html

▪ Majumder, R., Sarker, A., Emtiaz, S. M., & Khan, G. R. (2022). Effect of impact angle and energy conservation on the prompt splashing of a single droplet on a liquid pool. Book Chapter accepted for publication in Modeling and Analysis of Sustainable Renewable Energy System, LNE, Springer.

▪ Khan, G. R., Khan, M. T. (2022). Neutronic Calculation of Fuel Element of the Modular High-Temperature Gas-Cooled Reactor Benchmark Core Design with OpenMC Code. Accepted for presentation at the 4th International Conference on Energy and Power, Dec 2022

▪ Sarker, A., Khan, G. R. (2022). Numerical Analysis of Wettability Mediated Droplet Formation in the Dripping Regime of a Microfluidic T Junction. accepted for presentation at the 2nd International Conference on Mechanical Engineering and Applied Sciences, Dec 2022

Research Interests:

Nuclear Modeling and Simulation, Space Nuclear Power, Monte Carlo Particle Transport Method, Computational Fluid Dynamics.

Professional Experience:

Lecturer                                                                                                                Jul 2021 - Present

Department of Nuclear Science and Engineering

Military Institute of Science and Technology

                                                                           Courses Conducted

Honors and Awards:

Funded Projects:

▪ “Development and Thermal Hydraulic Analysis of Flow and Temperature Gradients of a One Fifth Scale

   LWR Fuel Pin Model” funded by the R&D Wing, Military Institute of Science and Technology, 2018-2019.

▪ “Development of a Robotic Vehicle to Monitor Radiation Level Remotely” funded by the Department of

   Nuclear Science and Engineering, Military Institute of Science and Technology, 2017

▪ Created teaching aid interactive desktop apps for conducting interactive class, funded by Udvash Academic

  Care, 2016

Software Skills:

Extracurricular Activities: