Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts
Author:
Funder
U.S. Department of Energy
U.S. DOE-NE Advanced Fuels Campaign
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference16 articles.
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4. Brown, N.R. et al., (2016). Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models (No. ORNL/TM-2016/729). Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States).
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