Monte Carlo Simülasyon Sonuçlarının Nükleer Reaktör Kalp Modelleme Yaklaşımlarına Duyarlılığının Araştırılması
نویسندگان
چکیده
Monte Carlo simulations provide accurate results for the neutronic response of system under consideration if modeling is performed appropriately since it has great influence on results. Sensitivity analysis approaches geometry and fissile material composition distributions in reactor core was by taking ITU TRIGA Mark II Research Reactor into consideration. The method defining fuel element positions using circular or hexagonal lattice considered as one case three different methods lumping compositions elements another these are used deterministic codes hence accuracy were also investigated. validation study showed that both MCNP Serpent resulted good agreement with experimental data. It observed handling ways did not significantly (up to 11.1 cents reactivity). However, arrangement more pronounced (deviation reactivity calculations around 1$). These deviations at may affect nuclear safety conclusion reactors having small shutdown margins. concluded users should be aware fact simplifications will result significant deviation from reality.
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ژورنال
عنوان ژورنال: Europan journal of science and technology
سال: 2022
ISSN: ['2148-2683']
DOI: https://doi.org/10.31590/ejosat.1065944