Learn the fundamentals of the thermohydraulic in nuclear reactors and the two-phase flow phenomena in LWRs. Students will learn the system code CATHARE used for the accidental transient simulations. Some notions of LWR transient analysis methodology with PIRT, Scaling, code development, verification and validation plus uncertainty quantification will also be given.

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‒ Basic knowledge of thermal hydraulics

‒ Basic knowledge of a system code

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By the end of the workshop, participants will:

‒Understand the fundamentals of the thermal hydraulics during complex nuclear transients.

‒Understand the general CATHARE behavior

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‒ Introduction to LWR thermal hydraulics: Two-phase phenomena in LWRs

‒ PIRT, Scaling, Code Development, Verification and Validation plus Uncertainty Quantification process

‒ System CATHARE code for accidental thermal hydraulic simulation

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