Journal
ANNALS OF NUCLEAR ENERGY
Volume 82, Issue -, Pages 142-150Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2014.08.024
Keywords
Serpent; Monte Carlo; Reactor physics; Homogenization; Burnup calculation
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Funding
- KAARME project in the Finnish Nation Research Programme on Nuclear Power Plant Safety (SAFIR)
- High Performance Monte Carlo Reactor Core Analysis (HPMC) Project within EU
- Academy of Finland Numerical Multi-physics project (NUMPS)
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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. (C) 2014 Elsevier Ltd. All rights reserved.
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