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...

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Bibliographic Details
Main Author: Kreher, Miriam A.
Other Authors: Forget, Benoit
Format: Thesis
Published: Massachusetts Institute of Technology 2023
Online Access:https://hdl.handle.net/1721.1/151199