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Showing 1 to 4 of 4 for “"Applied reactor physics"”.
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Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model
… of standard homogenization (SH) for full nuclearreactor-core neutronics calculations because its implementation does not require any changes to existing computer codes. Previous work found that single-cell SPH applied to Pressurized Heavy Water Reactors (PHWR) yields virtually no improvement …
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Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors
… calculations for Pressurized Heavy-Water Reactors (PHWRs) are usually performed in diffusion theory using an approximate core model, whereby only two energy groups are utilized and two-group neutronic properties (i.e. macroscopic cross sections and diffusion coefficients) are homogenized …
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Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.
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 node-homogenized models have historically been used whereby neutronic …
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Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several tens of energy groups. However, performing such detailed calculations for an entire core is prohibitively expensive from a …