Interim dry storage cask design for spent nuclear fuel discharged from VVER power reactor with an evaluation of its radiation and criticality safety Using MCNP5C & GETERA codes

Abstract

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 k_eff  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),(7.19 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.