Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

Munemichi Kawaguchi

Presentation information

Oral Presentation

III. Fission Energy Engineering » 306-1 Nuclear Safety Engineering, Nuclear Installation Safety, PSA

[3H14-17] Safety Evaluation on Fast Rector 2

Fri. Sep 9, 2016 3:50 PM - 4:55 PM Room H (Kumume City Plaza - Studio 3)

Chair: Satoshi Nishimura (CRIEPI)

3:50 PM - 4:05 PM

[3H14] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(13)Simulation of Na-concrete reaction process

*Munemichi Kawaguchi¹, Shinya Miyahara¹, Masayoshi Uno² (1.JAEA, 2.Fukui Univ.)

Keywords:Sodium-cooled Fast reactor, Sodium leak accident, Sodium-concrete reaction, Chemical reaction heat

The chemical reaction model of the sodium-concrete reaction in the case of the sodium leak accident with steel liner failar in sodium-cooled fast reactors has been developed by using COMSOL Multiphysics.