Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis
Annals of Nuclear Energy(2017)
Abstract
•Development and investigation of a Monte-Carlo module for transient neutronic analysis.•A transient module developed on the open-source Monte-Carlo static code OpenMC.•Treatment of delayed neutrons is inserted.•Simulation of precursors’ decay process is performed.•Transient analysis of simplified test-cases.
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Key words
Monte-Carlo,OpenMC,Kinetics,Transient,Delayed neutron,Precursor
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