Thanks to the growing computer power, it is now feasible to apply Monte Carlo methods to
the solution of non-stationary transport problems in reactor physics and in criticality-safety …

In the field of computational reactor physics, Monte-Carlo methodology is extensively used
in the analysis of static problems while the transient behavior of the reactor core is mostly …

Eigenvalue problems for neutron transport in random geometries are key for many
applications, ranging from reactor design to criticality safety. In this work we examine the …

Abstract The Iterated Fission Probability (IFP) method and Contributon-Linked eigenvalue
sensitivity/Uncertainty estimation via Track-length importance Characterization (CLUTCH) …

We perform simulations of two reactivity-insertion experiments in the SPERT III E-core
nuclear research reactor. The simulations use the TRIPOLI-4® Monte Carlo neutron …

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 …

This paper focuses on the development of a new computational model of the CNESTEN's
TRIGA Mark II research reactor using the 3D continuous energy Monte-Carlo code TRIPOLI …

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 …

The generation of accurate kinetic parameters such as mean generation time Λ and effective
delayed neutron fraction βeff via Monte Carlo codes is established. Employing these in …

In this paper we detail a Monte Carlo model for the SPERT III E-core and we illustrate the
simulation results obtained for the reactor physics parameters (including the effective …