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Showing 1 to 4 of 4 for “"Applied reactor physics"”.

  1. 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 …

    uoit Repository record for Investigation of a SPH-based sub-cell homogenization for PHWR using a multi-cell model (opens in a new tab)

  2. 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 …

    uoit Repository record for Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors (opens in a new tab)

  3. 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 …

    uoit Repository record for Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. (opens in a new tab)

  4. 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 …

    uoit Repository record for Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices (opens in a new tab)