Nuclear data uncertainty propagation to the Doppler coefficient of MYRRHA

Research output


This work investigates the impact of nuclear data on the uncertainty of the Doppler reactivity feedback effect for the MYRRHA fast reactor. Covariance matrices from the JEFF-3.3 and ENDF/B-VIII.0 nuclear data libraries were propagated using a stochastic sampling approach implemented with the SANDY code and the Monte Carlo particle transport code Serpent 2. This technique allowed us to derive an uncertainty bound for the Doppler coefficient that is only marginally affected by the statistical error of the Monte Carlo calculation.
Original languageEnglish
Number of pages10
StateUnpublished - 13 Aug 2023
Event2023 - M&C: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - Sheraton Fallsview Hotel, Niagara Falls
Duration: 13 Aug 202317 Aug 2023


Conference2023 - M&C
Abbreviated titleM&C2023
CityNiagara Falls

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