1. Accident Analysis for Nuclear Power Plants, Safety Reports Series No. 23. IAEA, Vienna, 2002.
2. On the validation and application of fluid-structure interaction analysis of reactor vessel internals at loss of coolants accidents;Andersson;Computer & Structures,2003
3. Nonlinear Finite Elements for Continua and Structures;Belytschko,2003
4. BNS I.11.1/2009, Requirements for deterministic safety analyses, UJD SR, Bratislava, October 2008.
5. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: PWR Vessel Internals;IAEA-TECDOC-1119,1999