In this work, the implementation of a collision history-based approach to
sensitivity/perturbation calculations in the Monte Carlo code SERPENT is discussed. The …

There is a rise in sensitivity and uncertainty analyses with respect to nuclear data, which are
a basis for a neutron transport simulation. The analyses are primarily concerned with the …

The need to perform eigenvalue sensitivity and uncertainty analysis with greater fidelity for
more complex systems has motivated the extension of the current multigroup sensitivity …

Precise knowledge of the effective delayed neutron fraction (βeff) and the corresponding
uncertainty is important for nuclear reactor safety analysis. The interest in developing the …

A sensitivity and uncertainty analysis was performed for the accelerator-driven system (ADS)
proposed by the Japan Atomic Energy Agency (JAEA) with the latest version of the …

The sensitivity analysis and the uncertainty quantification play an important role in improving
the evaluated nuclear data library. The current computational performance enables us to …

Experimental results of prompt neutron decay constant α is useful information to validate
numerical results of ω-eigenvalue for spatial and energetic fundamental mode. In order to …

A Windows interface XSUN‐2017 facilitating the deterministic radiation transport and cross‐
section sensitivity‐uncertainty (S/U) calculation is presented. The package was developed to …

The prompt fission neutron spectra covariance matrices of 235U, 238U and 239Pu were
evaluated using the Monte Carlo method for two empirical spectra formulations, Watt and …

The effective delayed neutron (β $ _ {eff} $) is a very important parameter for reactor and
criticality applications. This parameter is equal to the difference in reactivity between …