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Leakage-corrected fast reactor assembly calculation with Monte-Carlo code TRIPOLI4r and its validation methodology

Abstract : A leakage model based on B1 Homogeneous Equations has been recently implemented in continuous-energy Monte Carlo code TRIPOLI4. This leakage model algorithm iterates between the point-wise Monte Carlo simulation and a B1 Homogeneous Equations solver till reaching a final critical state in Monte Carlo simulation. The two advantages of our leakage model compared with the others are: we use critical flux spectrum to generate the multi-group constants for solving the B1 Homogeneous Equations; the leakage coefficients calculated are considered in point-wise Monte Carlo simulation. This leakage model is validated by a pre-designed numerical experiment simulated with continuous-energy TRIPOLI4 and the obtained results are also compared with those from SERPENT leakage model and deterministic leakage model in ECCO code. Finally, our leakage-corrected multi-group constants are used in transport theory based core calculation and they give out consistent multiplicative factor and neutronic balance.
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Submitted on : Wednesday, September 2, 2020 - 10:29:13 AM
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L. Cai, Y. Peneliau, J. Tommasi, J-F Vidal, C. Diop. Leakage-corrected fast reactor assembly calculation with Monte-Carlo code TRIPOLI4r and its validation methodology. Physor 2014 - The Role of Reactor Physics toward a Sustainable Future, Sep 2014, Kyoto, Japan. ⟨cea-02927951⟩

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