1. Preliminary assessment of the possible BWR core/vessel damage states for fukushima daiichi station blackout scenarios using RELAP/SCDAPSIM;Allison;Sci. Technol. Nucl. Install.,2012
2. Barbier, A., Cartier, O., Dolleans, P., Muller, T., Bellet, S., Fontes, J.-P., Alvarez, D., Longatte, E., 2009. Experimental characterization of hydraulics in the EPR{sup TM} lower plenum. Tests performed on the JULIETTE mock-up. Atomic Energy Society of Japan, Tokyo (Japan), Japan.
3. Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator;Bortot;Nucl. Eng. Des.,2011
4. Boyack, B.E., Lime, J.F., 1995. Intermediate-break LOCA analyses for the AP600 design, United States, p. Medium: ED; Size: 69 p.
5. Chen, S., Liu, Y., Tian, M., Tian, W., Qiu, S., Su, G., 2015. PWR core transient temperature numerical simulation based on porous media model. Nucl. Tech. 38, 090601-090601-090601-090606.