Neutron transport model based on the transmission probability method
Author:
Publisher
Elsevier BV
Subject
Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment
Reference10 articles.
1. Studies on production of neutrons in the spallation reactions using the Monte Carlo code MCNPX;Louis;Nucl Sci Eng,2012
2. Much ado about nothing: response matrices for void regions;Lewis;Ann Nucl Energy,2004
3. Transmission probability method of integral neutron-transport calculation for two-dimensional rectangular cells;Haeggblom;Nucl Sci Eng,1975
4. Application of the transmission probability method to the calculation of neutron-flux distributions in hexagonal geometry;Wasastjerna;Nucl Sci Eng,1979
5. Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem;Wu;Nucl Eng Des,2007
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