Modeling of SFR cores with Serpent-DYN3D codes sequence

E. Fridman; E. Shwageraus

doi:10.1016/j.anucene.2012.08.006

Modeling of SFR cores with Serpent-DYN3D codes sequence

E. Fridman, E. Shwageraus

Unit of Nuclear Engineering

Research output: Contribution to journal › Article › peer-review

47 Scopus citations

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.

Original language	English
Pages (from-to)	354-363
Number of pages	10
Journal	Annals of Nuclear Energy
Volume	53
DOIs	https://doi.org/10.1016/j.anucene.2012.08.006
State	Published - 1 Jan 2013

Keywords

DYN3D
ERANOS
Few-group cross-section generation
Lattice physics
Monte-Carlo
Serpent

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.1016/j.anucene.2012.08.006

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title = "Modeling of SFR cores with Serpent-DYN3D codes sequence",

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.",

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AU - Shwageraus, E.

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N2 - 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.

AB - 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.

KW - DYN3D

KW - ERANOS

KW - Few-group cross-section generation

KW - Lattice physics

KW - Monte-Carlo

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JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

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Modeling of SFR cores with Serpent-DYN3D codes sequence

Abstract

Keywords

ASJC Scopus subject areas

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