Impact on the criticality of the rupture of cladding materials in a transport package under accidental conditions of transport (ACT)

Safety-criticity analysis of a container carying Mox fuel assemblies. These kind of containers are used to carry fuel around the world, especially in France, between the nuclear power plant and the reprocessing plant in La Hague (next to the Flamanville's EPR). As you may know, the AIEA has emited strong recomandations concerning the transport of nuclear fissil material. The Autorité de Sûreté Nucléaire (the French equivalent of AIEA) is the safety authority charged to make sure that Orano, my company, is respecting these rules. Among them there is the respect of the safety-criticity criteria: make sure that the fissil material has a keff<0.950 pcm. Therefore, my job here, is to use stochastic code using Monte Carlo method (TRIPOLI4.8, APOLLO2-MORET5) to ensure the respect of this criteria.