Investigation of discretization uncertainty in Monte Carlo neutron transport simulations of the Molten Salt Fast Reactor (MSFR)

Investigation of discretization uncertainty in Monte Carlo neutron transport simulations of the Molten Salt Fast Reactor (MSFR)

In the present work, an assessment of the Neutronic Benchmark of the Molten Salt Fast Reactor (MSFR) was performed using mesh based Monte Carlo Neutron Transport (MCNT) calculations with numerical uncertainty quantification due to discretization in neutronic parameters. Calculations with Constructi...

Full description

Bibliographic Details
Main Authors: Tiago Augusto Santiago Vieira, Felipe Reis Campanha Ribeiro, Yasmim Martins Carvalho, Vitor Vasconcelos Araújo Silva, Graiciany de Paula Barros, Andre Augusto Campagnole dos Santos
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2023-12-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
MSFR
Neutronics
Monte Carlo
Extended GCI
Mesh based simulation
Online Access:https://www.sbpr.org.br/revista/index.php/REVISTA/article/view/1317

Internet

https://www.sbpr.org.br/revista/index.php/REVISTA/article/view/1317

Similar Items