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This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neutron fraction  β  eff  for critical and subcritical cores of the MYRRHA reactor using the continuous-energy Monte Carlo N-Particle transport code MCNP. The  β  eff  sensitivities are calculated by the modified  k -ratio method proposed by Chiba. Comparing the  β  eff  sensitivities obtained with different scaling factors  a  introduced by Chiba shows that a value of  a  = 20 is the most suitable for the uncertainty quantification of  β  eff . Using the calculated  β  eff  sensitivities and the JENDL-4.0u covariance data, the  β  eff  uncertainties for the critical and subcritical cores are determined to be 2.2 ± 0.2% and 2.0 ± 0.2%, respectively, which are dominated by delayed neutron yield of  239 Pu and  238 U.

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

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