Abstract
The study of nuclear fuel is considered very important. This is because those chemical reactions are normally occurring due to the continuous, instance irradiation to the fuel material during the operation of reactor. In order to improve the fuel fabrication process and develop them further, the determination of fission product as well as their distribution over the entire length of the fuel pin swelling. The Cs – 137 was chosen as a precursor for the burn up level of the irradiated fuel and the universal code ORIGENwas used to study the irradiated fuel pin UO2 and to calculate the level of its burn up for some irradiation condition.
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