1. CERTA-TN, Consolidation of Integral System Experimental Databases for Reactor Thermal-hydraulic Safety Analyses;Addabbo,2003
2. Status Report on Relevant Thermal-hydraulic Aspects of Advanced Reactor Designs;Aksan,1996
3. Aksan, S.N., D'Auria, F., Glaeser, H., Lillington, J., Pochard, R., Sjoberg, A., 1997. Systematic evaluation of the CSNI SET Validation Matrix data base and resulting needs. In: ASME-JSME Int. Conf. on Nuclear Engineering (ICONE5-2147), Nice (F), May 26–30.
4. Aksan, S.N., Schulenberg, T., Squarer, D., Cheng, X., Struwe, D., Sanchez, V., Dumaz, P., Kyrki-Rajamaki, R., Bittermann, D., Souyri, A., Oka, Y., Koshizuka, S., 2003. Potential Safety Features and Safety Analysis Aspects For High Performance Light Water Reactor (HPLWR). In: Int. Conf. on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Kyoto (J).
5. Target phenomena in nuclear thermal-hydraulics;Aksan,2017