Browsing Faculty of Energy Systems & Nuclear Science by Subject "Advanced homogenization"
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Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. (2014-08-01)The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the core. Since this is computationally impractical, approximate ...