الفهرس 
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Abstract
Research reactors are considered to be important for research activities like irradiation, some in Boron Neutron Capture Therapy (BNCT) and education to teach the basics of the field to the new young generation in the field of nuclear science and engineering. The aim of this research is to reduce the waste of the Pressurized Water Reactor (PWR) spent fuel by irradiating the PWR spent fuel in a research reactor core by installing Accelerated Driven neutron in the research reactor system. In this work the fuel pin of the PWR fuel is modelled and burned for 3 years in a infinite surface, then it taken out and left for cooling for 10 years, then irradiated for three years by neutron source generate neutron with 36.3 MeV. The type of research reactor used in this research is CROCUS research reactor which is used by Ecole Polytechnique Federale de Lausanne (EPFL), for the purpose of education in the university. The modelling and simulation is conducted by the probabilistic code Monte Carlo N-Particle version 2.7.0 (MCNPX). The results show that, the ADS system can be used in CROCUS research reactor to irradiate spent fuel, and it reduced wastes of the spent fuel from PWR by 16.34%. This proves that a research reactor with cylinder fuel rods and a central control rod can be used as ADS by replacing the central control rod by a neutron generator and the fuel by a spent fuel.