Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code

Ville Rintala (Corresponding Author), Heikki Suikkanen, Jaakko Leppänen, Riitta Kyrki-Rajamäki

Research output: Contribution to journalArticleScientificpeer-review

8 Citations (Scopus)

Abstract

This paper documents the models available in Serpent for high temperature reactor (HTR) calculations. It is supplemented by a calculation example of ASTRA critical pebble bed experiments. In the pebble bed reactor modeling, different methods have been used to model the double heterogeneity problem occurring in pebble bed reactor calculations. A solution was sought to avoid unphysical simplifications in the pebble bed modeling and the stochastic geometry modeling features available in the Monte Carlo code Serpent were applied for exact placement of pebbles and fuel particles. Randomly packed pebble beds were produced in discrete element method (DEM) simulations and fuel particles were positioned randomly inside the pebbles. Pebbles and particles are located using a Cartesian search mesh, which provides necessary computational efficiency. Serpent uses Woodcock delta-tracking which provides efficient neutron tracking in the complicated geometries. This detailed pebble bed modeling approach was tested by calculating the ASTRA criticality benchmark experiment done at the Kurchatov Institute in 2004. The calculation results are in line with the sample calculations provided with the benchmark documentation. The material library selected for the calculations has a major effect on the results. The difference in graphite absorption cross section is considered the cause of this result. The model added in Serpent is very efficient with a calculation time slightly higher than with a regular lattice approximation. It is demonstrated that Serpent can be used for pebble bed reactor calculations with minimal geometric approximations as it allows exact pebble bed modeling with randomly positioned fuel particles and locations of pebbles produced by DEM. Due to the added stochastic geometry features and efficient neutron tracking, it is concluded that Serpent is well suited for the calculations of HTRs.
Original languageEnglish
Pages (from-to)223-230
JournalAnnals of Nuclear Energy
Volume77
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

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Pebble bed reactors
Geometry
Finite difference method
Neutrons
High temperature reactors
Computational efficiency
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Keywords

  • high temperature reactor
  • pebble bed reactor
  • reactor physics
  • Monte Carlo
  • sicrete element method

Cite this

Rintala, Ville ; Suikkanen, Heikki ; Leppänen, Jaakko ; Kyrki-Rajamäki, Riitta. / Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code. In: Annals of Nuclear Energy. 2015 ; Vol. 77. pp. 223-230.
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Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code. / Rintala, Ville (Corresponding Author); Suikkanen, Heikki; Leppänen, Jaakko; Kyrki-Rajamäki, Riitta.

In: Annals of Nuclear Energy, Vol. 77, 2015, p. 223-230.

Research output: Contribution to journalArticleScientificpeer-review

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