Subchannel void distribution correction model for the two-stage core analysis method in boiling water reactors
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference11 articles.
1. Effect of radial void distribution within fuel assembly on assembly neutronic characteristics;Ama;J. Nucl. Sci. Technol.,2002
2. BWR core simulator using three-dimensional direct response matrix and analysis of cold critical experiments;Hino;J. Nucl. Sci. Technol.,2010
3. Effect of Subchannel void fraction distribution on lattice physics parameters for boiling water reactor fuel bundles;Ikehara;J. Nucl. Sci. Technol.,2008
4. three-dimensional direct response matrix method using a Monte Carlo calculation;Ishii;J. Nucl. Sci. Technol.,2009
5. Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly;Jatuff;Ann. Nucl. Energy,2006
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1. A kinetic model for the direct response matrix method;Journal of Nuclear Science and Technology;2019-08-30
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