Abstract
This paper presents the delta-tracking based geometry routine used in
the Serpent Monte Carlo reactor physics burnup calculation code. The
method is considered a fast and efficient alternative to the
conventional surface-to-surface ray-tracing, and well suited to the
lattice physics applications for which the code is mainly intended. The
advantages and limitations of the routine are discussed and the
applicability put to test in four example cases. It is concluded that
the method performs well in LWR lattice applications, but really shows
its efficiency when modeling HTGR particle fuels.
Original language | English |
---|---|
Pages (from-to) | 715-722 |
Number of pages | 8 |
Journal | Annals of Nuclear Energy |
Volume | 37 |
Issue number | 5 |
DOIs | |
Publication status | Published - 2010 |
MoE publication type | A1 Journal article-refereed |