1. State-of-the-Art Reactor Consequence Analyses Project;Bixler,2013
2. Carbajo, J.J. 1993. Severe Accident Source Term Characteristics for Selected Peach Bottom Sequences Predicted by the MELCOR Code, NUREG/CR-5942. Oak Ridge, TN 37831-6285: U.S. Nuclear Regulatory Commission.
3. Main modelling features of the ASTEC V2.1 major version;Chatelard;Ann. Nucl. Energy,2016
4. Chatelard, P., F. Gabrielli, F. Fichot, H. Bonneville, C. Bouillet, S. Belon, L. Chailan, and V.H. Sanchez Espinoza. 2017. Contribution of ASTEC numerical simulations to the understanding of the Fukushima accidents. Vienna: IAEA Workshop on Advances in Understanding the Progression of Severe Accidents in Boiling Water Reactors.
5. MAAP4 Applications Guidance, Desktop Reference for Using MAAP4 Software, Revision 2;EPRI,2010