Article ID Journal Published Year Pages File Type
1728779 Annals of Nuclear Energy 2013 10 Pages PDF
Abstract

DYN3D reactor dynamics nodal diffusion code was originally developed for the analysis of Light Water Reactors. In this paper, we demonstrate the feasibility of using DYN3D for modeling of fast spectrum reactors. A homogenized cross sections data library was generated using continuous energy Monte-Carlo code Serpent which provides significant modeling flexibility compared with traditional deterministic lattice transport codes and tolerable execution time. A representative sodium cooled fast reactor core was modeled with the Serpent–DYN3D code sequence and the results were compared with those produced by ERANOS code and with a 3D full core Monte-Carlo solution. Very good agreement between the codes was observed for the core integral parameters and power distribution suggesting that the DYN3D code with cross section library generated using Serpent can be reliably used for the analysis of fast reactors.

► Serpent–DYN3D sequence was used for the analysis of an SFR core. ► Homogenized cross sections were generated using Monte-Carlo code Serpent. ► The full core analysis was performed with the nodal diffusion code DYN3D. ► The DYN3D results were compared with those of ERANOS and full core Monte-Carlo solution.

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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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