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. 2021;35(2). Accessed June 18, 2026. https://journal.damascusuniversity.edu.sy/index.php/basj/article/view/1036