Ongoing Projects
Ongoing Projects
Embedded Files
1. Development of a coupled multi physics LWR nuclear reactor fuel performance analysis program
1. Development of a coupled multi physics LWR nuclear reactor fuel performance analysis program
Project Team:
PI: Md Tanvir Ahmed,Collaborator : Ebny Walid Ahammed Thesis student : Abdur Rahman Antor
Project Description : This will be a computer code that calculates the steady-state response of light-water reactor fuel rods during long-term burnup. The code will calculate the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena will be modeled by the code include:
The code will contain necessary material properties,water properties, and heat-transfer correlations.
PI: Md Tanvir Ahmed,Collaborator : Ebny Walid Ahammed Thesis student : Abdur Rahman Antor
Project Description : This will be a computer code that calculates the steady-state response of light-water reactor fuel rods during long-term burnup. The code will calculate the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena will be modeled by the code include:
- heat conduction through the fuel and cladding to the coolant
- cladding elastic and plastic deformation
- fuel-cladding mechanical interaction
- fission gas release from the fuel and rod internal pressure
- cladding oxidation.
The code will contain necessary material properties,water properties, and heat-transfer correlations.
2.Core Neutronics Characterization of the Allegro-75 Gas Cooled Fast Reactor
Project Team:PI: Md Tanvir AhmedThesis Student: Shohanul IslamProject Description: By using OpenMC simulation code, neutronics analysis of Allegro-75 GFR will be conducted for various core configurations along with inspecting a wide range of proposed fuel, cladding, and reflector materials. The neutronics analysis includes:
- Effective Multiplication Factor, Neutron Flux, Fission Rate, Power Density Distribution
- A Comprehensive Depletion Analysis for Each Model
- Mass Evolution of Fissile & Fertile Nuclide, Neutron Leakage Analysis
- Doppler Constant, Moderator Temperature Coefficient, Effective Delayed Neutron Fraction
- Axial & Radial Expansion Coefficient, Power Peaking Factor (PPF), Sensitivity Analysis
- Effective Full Power Year, Breeding Ratio, Control Rod Worth
3. Enhancing Neutronic Performance: A Comparative Study of Reflectors in Radially and Axially Heterogeneous Cores for ABR-1000 Sodium Cooled Fast Reactor
Project Team:
PI: Md. Tanvir AhmedThesis Student: Md. Hasebul Hasan NiloyProject Description: It’s a simulation project where the effectiveness of different reflective materials such as pure lead, Ba2Pb, BeO, SiC, PbO, Graphite, HT9, and Zr3Si2 will be studied to find the optimal reflector for the Radially and Axially Heterogeneous Cores for ABR-1000 Sodium Cooled Fast Reactor. OpenMC with ENDF/B-VIII.0 nuclear data will be used to conduct the project. The study will include:
- Depletion analysis for several reflector materials.
- Flux distribution for various reflector materials at the beginning of life (BOL) and the end of life (EOL).
- Fission rate distribution for various reflector materials at BOL and EOL.
- The evolution of toxic and fissile isotopes for various reflector materials.
- Total neutron leakage for various materials used as reflectors.
- Axial flux distribution for various reflector materials at BOL and EOL.
4. Elemental Analysis of the Meghna River Sediment by Neutron Activation Analysis (NAA)
Project Team:PI: Md Tanvir AhmedCo-supervisor: Dr. Mohammad Amirul Islam, Chief Scientific Officer, INST, AERE, BAECThesis Student: Mehedi Hasan
Project Description: The project aims to conduct an elemental analysis of the Meghna River sediment using Neutron Activation Analysis (NAA). Elemental analysis includes:
Project Description: The project aims to conduct an elemental analysis of the Meghna River sediment using Neutron Activation Analysis (NAA). Elemental analysis includes:
- Sample Collection
- Sample Preparation
- Neutron Activation Analysis (NAA)
- Quality Control
- Data Analysis
Get in touch with us
Get in touch with us
We are located at 1st floor (NE), Science Workshop, Curzon Hall area at the University of Dhaka.
Email: mta@du.ac.bd
Phone: +8801855316252
from Sunday to Thursday (9.00 am to 5.00 pm)
Page updated
Google Sites
Report abuse