[1H13-17] Innovative Reactor

[1H16] Neutronics - thermal hydraulics behavior of inclined offshore floating BWR

*Kodai Fukuda¹, Kenya Suyama¹, Toru Obara² (1. JAEA, 2. Tokyo Tech)

Keywords:Kinetics analysis, Offshore nuclear power plant, Neutronics-thermal hydraulics coupled analysis

In recent years, efforts have been made in Japan to develop an offshore nuclear power plant with BWR. The effects of the marine environment, such as an inclination, to the reactor behavior are considered to be clarified. In this presentation, the result of the preliminary neutronics - thermal hydraulics coupled analysis, which aims for the clarification of the reactor behavior when BWR is inclined, is reported. The reactor system code TRACE and neutronics code PARCS are used for the analysis. The Peach Bottom 2 is modeled and analyzed for the preliminary analysis.