تصميم حاوية تخزين جاف مؤقت للوقود النووي المستنفذ في مفاعل طاقة من النوع VVER و دراسة أمنها الحرجي و الإشعاعي باستعمال الكودين MCNP5-beta و GETERA

الملخص EN

MCNP5-beta code was used to model an Interim dry storage cask for some spent nuclear fuel assemblies which are burned up in VVER1000 power reactor using GETERA code and then evaluate the validation of this model by calculating neutron multiplication factor keff inside the cask through regular storage case and an accident case supposes nuclear content being flooded with water, and its value was (0.35633),(0.98569) consecutively, in addition to calculate the neutron and photon radiation dose rate in several meaningful points outside the cask where workers are expected to be exposed, since the maximum value was (113.7 mrem/h),(7.99 mrem/h) consecutively.

The obtained results have showed a good agreement with recommended international dose values from International Atomic Energy Agency reports and some similar theoretical studies.