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...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
| Published: |
EDP Sciences
2018-01-01
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| Series: | EPJ Nuclear Sciences & Technologies |
| Online Access: | https://doi.org/10.1051/epjn/2018023 |