Speaker
Description
Very small modular nuclear reactors (vSMR), or micro-reactors, are identified as a potential means to provide reliable and cost-effective power between 1 and 10 MWe for remote installations. This paper presents a neutronic optimization study of sodium gas-cooled Micro Modular Reactor (MMR) design that has been simulated using the Monte Carlo method. As a high fidelity open source Monte Carlo code, OpenMC has been used to simulate the neutron flux distribution, power and burnup of the reactor core using ENDF-B/VII.1 data library.
This Micro Modular Reactor is a 5MWe power reactor with a 20-year lifetime without refuelling, designed to operate in a fast spectrum with TRISO Fuel because TRISO particles are the leading-edge nuclear fuel form that is structurally more resistant to neutron irradiation, corrosion, oxidation and high temperature than traditional reactor fuel. TRISO fuels comprise thousands of micro-encapsulated uranium-bearing fuel kernels and are individually coated with multiple layers of pyrolytic carbon and silicon carbide that act as their own containment. This reactor model has a hexagonal unit cell with a Sodium-cooled heat pipe in the center surrounded by the TRISO particles embedded in a beryllium matrix.
| Country OR International Organization | Bangladesh (Nationality), McMaster University |
|---|---|
| Email address | razianushrat@gmail.com, nushratr@mcmaster.ca |
| Confirm that the work is original and has not been published anywhere else | YES |
