الفهرس 
Transient study of pressurized water reactor (PWR) with different nuclear fuel types
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Abstract
This study involved Mathematical modeling of the PWR based on lumped parameters technique, this model includes the neutronics, core heat transfer and piping. A computer code of PWR is designed by FORTRAN language to study the dynamic performance in the steady state and transient conditions using different fuels: UO₂, ThO₂ {u2212} UO₂ and U {u2212} ZrH₁.₆, which shows the priority of each in these transients. Also, an experimental simulation for a cylindrical reactor (like PWR) was performed using Cf²⁵² to study the neutrons and Þ-rays decay through a water/iron bi-layer assembly