Convergence assessment of the MCNP5 model for NUR research reactor

In recent years, the Monte Carlo (MC) methods have become an extensive and reference tool for criticality calculations. Despite the high precision that could be reached in MC modeling, the criticality calculations are still faced with the problem of fission source convergence leading, thereby, in so...

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Bibliographische Detailangaben

Hauptverfasser:	Mokhtari, O., Mazrou, H.
Format:	Tagungsbericht
Sprache:	eng
Schlagworte:	Computer simulation Convergence Entropy (Information theory) Fission Mathematical models Monte Carlo simulation Multiplication Multiplication & division Neutrons Nuclear engineering Nuclear fuels Nuclear safety
Online-Zugang:	Volltext
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