The kinetics parameters, namely the effective delayed neutron fraction (β eff) and the
generation time (Ʌ), of the first core of RSG GAS (MPR-30) multipurpose reactor were, for …

Abstract Since the 1960s, Monte Carlo methods have been used to compute the effect of
perturbations on system responses and for computing sensitivity coefficients. This review …

A Monte Carlo method is developed that performs adjoint-weighted tallies in continuous-
energy k-eigenvalue calculations. Each contribution to a tally score is weighted by an …

New algorithms and techniques are developed for calculating the iterated fission probability
(IFP) using a Monte Carlo eigenvalue calculation scheme. The proportionality of the …

The need to model geometrically complex systems with improved ease of use and fidelity
and the desire to extend the Tools for Sensitivity and UNcertainty Analysis Methodology …

The analysis of neutron kinetics relies on the knowledge of adjoint-weighted kinetics
parameters, which are key to safety issues in the context of transient or accidental reactor …

Abstract The so-called Iterated Fission Probability (IFP) method has provided a major
breakthrough for the calculation of the adjoint flux and more generally of adjoint-weighted …

Exploiting a fluid dynamic formulation for which a probabilistic counterpart might not be
available, we extend the theory of Schrödinger bridges to the case of inertial particles with …

The experimental configurations, the construction data and the material compositions of the
CROCUS reactor, a water-moderated zero-power core operated at the Ecole Polytechnique …

New methods are proposed to estimate the effective delayed neutron fraction βeff in Monte
Carlo calculations: the eigenvalue methods jointly used with the differential operator …