Results 141 to 150 of about 788 (153)
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ARRC: A random ray neutron transport code for nuclear reactor simulation
Annals of Nuclear Energy, 2018John R Tramm +2 more
exaly
A POD reduced-order model for resolving the neutron transport problems of nuclear reactor
Annals of Nuclear Energy, 2020exaly
Application of the fractional neutron point kinetic equation: Start-up of a nuclear reactor
Annals of Nuclear Energy, 2012Gilberto Espinosa-Paredes
exaly
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor
Nuclear Engineering and Design, 2019Eric Cervi +2 more
exaly

