[2J01-09] Breakage Prevention of Containment Vessel

[2J01] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(17)Outline

*Masayoshi UNO¹, MItsuhiro AOYAGI², Tadashi WATANABE¹, Munemichi KAWAGUCHI², Ikuo YAMAMOTO¹, Daisuke DOI², Kei Itho², Hiroki YADA², Masanori ANDO² (1. Research Institute of Nuclear Engineering, University of Fukui, 2. Japan Atomic Energy Agency)

Keywords:Sodium cooled fast reactor, severe accident, Failure of continer vessel

Outline of research, "Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor" by Fukui University in cooperation with Japan Atomic Energy Agency supported by MEXT from 2013 to 2016 is presented.