Modeling Feedback Effects of Transient Nuclear Systems Using Monte Carlo

Monte Carlo neutron transport is the gold standard for accurate neutronics simulation of nuclear reactors in steady-state because each term of the neutron transport equation can be directly tallied using continuous-energy cross sections rather than needing to make approximations in energy, angle, or...

ver descrição completa

Detalhes bibliográficos
Autor principal: Kreher, Miriam A.
Outros Autores: Forget, Benoit
Formato: Tese
Publicado em: Massachusetts Institute of Technology 2023
Acesso em linha:https://hdl.handle.net/1721.1/151199