Abstract
The Serpent Monte Carlo reactor physics burnup
calculation code has been developed at VTT Technical
Research Centre of Finland since 2004, and is currently
used in over 100 universities and research organizations
around the world. This paper presents the brief history
of the project, together with the currently available
methods and capabilities and plans for future work.
Typical user applications are introduced in the form of a
summary review on Serpent-related publications over the
past few years.
Original language | English |
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Pages (from-to) | 142-150 |
Journal | Annals of Nuclear Energy |
Volume | 82 |
DOIs | |
Publication status | Published - 2014 |
MoE publication type | A2 Review article in a scientific journal |
Event | Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA + MC 2013. Pluri- and Trans-disciplinarity, Towards New Modeling and Numerical Simulation Paradigms - Paris, France Duration: 27 Oct 2013 → 31 Oct 2013 |
Keywords
- Serpent
- Monte Carlo
- reactor physics
- homogenization
- burnup calculation