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    Öğe
    A methodology to solve computational power issue for high fidelity loose and explicit Monte Carlo-CFD coupled multi-physics analysis for block type HTGRs
    (Pergamon-Elsevier Science Ltd, 2026) Lule, Senem Senturk; Sayin, Sefa; Kutbay, Feride; Bircan, Muhammed Mustafa; Colak, Uner
    High Temperature Gas Cooled Reactors (HTGRs) offer wide range of applications besides electricity generation therefore different designs are under development with multi-physics modeling. Although neutronic calculations of block type HTGRs are quite straight forward, thermal-hydraulic calculations are challenging due to complex heat transfer mechanism in the core. In addition, if high fidelity is applied, the computational power and time requirement is quite high. The high fidelity, loose, and explicit coupling multi-physics approach with Monte Carlo and computational fluid dynamics codes was proposed in this study that minimizes the computational power need without losing accuracy. The proposed methodology was tested with Holos Quad Core microreactor. The calculations showed that both neutronic and thermal-hydraulic simulation results of the proposed methodology are within 4% difference level with the results given for Holos microreactor therefore showing the proposed methodology's reliability.
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    Öğe
    New thorium core loading patterns for high temperature gas cooled nuclear microreactors
    (Pergamon-Elsevier Science Ltd, 2025) Lule, Senem Senturk; Bircan, Muhammed Mustafa; Kutbay, Feride; Sayin, Sefa; Colak, Uner
    Ten different 50:50 vol ratio thorium core loading configurations for a chosen HTGR microreactor were compared with original uranium core loading from neutronics point of view. 2.72 x 109 individual TRISO particles except for homogeneous fuel configuration were modeled. The best configuration was achieved when fuel channels with three layer axial ThCO-UCO-ThCO seed/blanket were placed in the core as radial seed/blanket configuration with ThCO filled fuel channels. With thorium loading, initial criticality was reduced from 1.301 to 1.2619 and EFPD from 3500 days to 1775 days but power generation, power peaking factor, and maximum axial power peaking factor in the highest power producing fuel channel were increased therefore the burnable poison distribution optimization was performed to reduce these parameters. When compared with 20.35 kW, 2.13, and 1.3 values for aforementioned parameters for uranium configuration, 20.70 kW, 2.17 and 1.70 values for thorium core loading are acceptable.