Formulation Of A High-Fidelity Nuclear Fission Sites Convergence Detection Method In Monte Carlo Reactor Safety Assessments

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Formulation Of A High-Fidelity Nuclear Fission Sites Convergence Detection Method In Monte Carlo Reactor Safety Assessments

Monte Carlo (MC) neutron transport simulation is a widely used computational tool for assessing the safety of various nuclear technologies, including nuclear reactors. During the simulation, an initial guess of the neutron source distribution is required, and as several MC cycles are simulated, it...

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Bibliographic Details
Main Author:	Chin, Ken Fui
Format:	Thesis
Language:	English
Published:	2023
Subjects:	QC1-999 Physics
Online Access:	http://eprints.usm.my/62919/ http://eprints.usm.my/62919/1/Pages%20from%20CHIN%20KEN%20FUI%20-%20TESIS.pdf

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