Sensitivity and uncertainty analysis of βeff for MYRRHA using a Monte Carlo technique

Sensitivity and uncertainty analysis of βeff for MYRRHA using a Monte Carlo technique

This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neutron fraction βeff for critical and subcritical cores of the MYRRHA reactor using the continuous-energy Monte Carlo N-Particle transport code MCNP. The βeff sensitivities are calculated by the modifie...

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Bibliographic Details
Main Authors: Iwamoto Hiroki, Stakovskiy Alexey, Fiorito Luca, Van den Eynde Gert
Format: Article
Language:English
Published: EDP Sciences 2018-01-01
Series:EPJ Nuclear Sciences & Technologies
Online Access:https://doi.org/10.1051/epjn/2018023

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