1. Sensitivity and Uncertainty Analysis of Nuclear Data for the Metallic-Fueled ABR-1000 Sodium-Cooled Fast Reactor Open Access Author: Shi, Jun Title: Sensitivity and Uncertainty Analysis of Nuclear Data for the Metallic-Fueled ABR-1000 Sodium-Cooled Fast Reactor Graduate Program: Nuclear Engineering Keywords: UncertaintySodium-Cooled Fast ReactorTransientCovariance File: Download Jun_Shi-Master_Thesis.pdf Committee Members: Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor
