، صفحه 0-0 (1) اصل مقاله (579.62 K)

عنوان دوره: اولین دوره بین المللی و بیست و هشتمین دوره ملی (1400)

Sajjad Hassanpour؛ kamal Hadad

Many calculation in the reactor core requires solving the Boltzmann neutron transport equation, which due to the complexity of this equation, numerical methods are used to solve it. Results of numerical solution can be trusted when corrections of the resonance self-shielding effect (Which is just one of the effective parameters) are included and new cross sections are obtained. These corrections can be made by a method called the subgroup method and can be done through deterministic code such as DRAGON. Therefore, the resonance self-shielding effect calculation has been performed for fuel of unit-2 of Bushehr Nuclear Power Plant and its results have been matched with the results of MCNP code (Although this kind of calculations inherently has a degree of uncertainty).

Resonance self-shielding؛ DRAGON code؛ MCNP code؛ Fuel rod

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