2017 Annual Meeting

Presentation information

Oral presentation

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

[2M15-18] Safety Evaluation on Fast Reactor 2

Tue. Mar 28, 2017 4:05 PM - 5:10 PM Room M (16-504 Building No.16)

Chair: Hiroshi Endo (CRIEPI)

4:05 PM - 4:20 PM

[2M15] Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor

(14)Self-terminating behavior of sodium-concrete reaction

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

Keywords:sodium-cooled Fast reactor, sodium-leak accident, sodium-concrete reaction, self-termination, reaction product

A sodium-concrete reaction is one of the important phenomena to cause the release of hydrogen gas in the case of sodium-leak accident of sodium-cooled fast reactors. In this study, the series of experiments on the transport behavior of the reactants were performed to investigate the self-termination behavior. As the results, the chemical reaction of the interface has important role in the concrete ablation, and it was founded that the self-termination behavior was caused by preventing the transport of the reactants for the reaction products sediment.