Thermal influence on steam generator heat transfer tube during sodium-water reaction accident of sodium-cooled fast reactor

Yamaguchi, Akira*; Takata, Takashi*; Ohshima, Hiroyuki; Kurihara, Akikazu 

A breach of the heat transfer tube (HTT) in a steam generator (SG) of a Sodium Fast Reactor causes sodium-water reaction. The design and safety concern is a possibility of the secondary failure of nearby HTTs that could cause undesirable development of the accident. One needs to evaluate the temperature transients of the HTTs in the reaction region for safety evaluation. In the present study, a computational method is developed for this purpose. It solves the sodium thermal-hydraulics and the heat conduction in the adjacent HTTs. An experiment performed at JAEA is analyzed with the method developed in this study. It is found that analyzed temperatures are in good agreement with the experimental data. Based to the experimental and computational results, multi-phase multi-component flow characteristics are depicted. Furthermore, the heat transfer coefficient is evaluated using the numerical simulation result.