The aim of the thesis is the assessment and validation of numerical models for the prediction of detailed subchannel distribution and departure from nucleate boiling (DNB) to a full scale data on a prototypical PWR rod bundle. To carry out this goal the participant will used TRACE, a software designed by the United State Nuclear Regulatoey Commision. The student should study implications on reactor design and safety analyses, propose changes/additions to reactor design and propose new experiments. The thesis is composed ny the following sections: - Introduction - Description of the Facility - Description of the Method - Description of the Model - Results - Conclusions

Outgoing