Calculation codes 2

The ASTEC software system

The ASTEC (Accident Source Term Evaluation Code) software system simulates all the phenomena involved in a core meltdown accident in a water-cooled reactor, from the initiating event to the release of radioactive products (known as the "source term") outside the containment

FUEL+

The aim of the FUEL+ software platform is to model the behaviour of nuclear fuel during normal, incidental and accidental operation, as well as during storage in a deactivation pool and transport for reprocessing

SCANAIR

The purpose of the SCANAIR (Système de Codes pour l'ANalyse d'Accidents d'Insertion de Réactivité) calculation code is to simulate the thermomechanical behaviour of a fuel rod during a Reactivity Initiated Accident (RIA) in a pressurised water reactor (PWR)

DRACCAR

The Draccar calculation software simulates a loss-of-coolant accident following, for example, the loss of reactor core cooling water or the dewatering of a fuel storage pool

The Moret code is a Monte Carlo code that simulates neutron transport in three-dimensional space

SYMBIOSE

The Symbiose software platform can be used to simulate the impact on humans of radioactive contamination in the environment: it models the transport and transfer of the radiation source to the various environmental compartments, enabling the dose received by humans to be calculated

EDEN

Eden calculates dose coefficients for non-human organisms, depending on their internal and external exposure conditions, for alpha, beta and gamma radiation from any radionuclide