Browsing by Author "Carisse, Katarzyna"
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Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. Carisse, Katarzyna (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 ...