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 . مجلة العلوم الأساسية [Internet]. 2021 Aug. 19 [cited 2026 Jun. 18];35(2). Available from: https://journal.damascusuniversity.edu.sy/index.php/basj/article/view/1036