Abstract

ANICCA is a new nuclear fuel cycle scenario code that is being developed by SCK•CEN in close collaboration with an industrial partner. The purpose of ANICCA is to simulate any nuclear fuel cycle scenario with their associated facilities, covering from the uranium mining to the final disposal of the spent fuel and reprocessing waste, including the fuel burnup process, which is still under development. The work presented has two purposes: showing the capabilities of the code and testing the new improvements developed. The scenario chosen concerns the Belgian nuclear fuel cycle. This scenario considers two options: the first one consists of a phase out of the current status of the fleet – a classical open fuel cycle where a mono recycling strategy was a applied for a short period of time– and the second one, which is like the first option, but includes an ADS at the end of the cycle, to show the advantages of deploying this type of facility. In the analysis, several parameters were calculated, such as: Natural uranium requirements, fuel or separated material mass needed, long term decay heat and radiotoxicity – among others. Results show consistency with the estimations made in related studies, despite the fact that the code is still under development.