Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code

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Abstract

This paper describes the methodology used by the Monte Carlo particle transport code Serpent to produce homogenized microscopic cross sections. The microscopic cross sections can be used for multiple purposes for example in nodal programs. The current implementation is presented together with its features and limitations. The methodology is demonstrated by calculating the activation of structural materials in two simple test problems with Serpent and the nodal neutronics program Ants utilizing Serpent-generated group constants.
Original languageEnglish
Article number108603
JournalAnnals of Nuclear Energy
Volume164
DOIs
Publication statusPublished - 15 Dec 2021
MoE publication typeA1 Journal article-refereed

Keywords

  • Homogenization
  • Microscopic cross sections
  • Microscopic depletion
  • Serpent

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