Coding of model for sodium-water reaction products transport

not registered; Kishida, Masako*; not registered; not registered

The LMFBR concept without secondary sodium system is considered to be one of the most promising concepts for plant cost reductions. In this type of LMFBR, steam generators(SGs) are directly equipped in the primary sodium system. Therefore, the evaluation of effects of sodium-water reaction products (SWRPs) to the reactor core in case of SG tube rupture becomes one of the major safety issues. In this work, SMAC-13E, the thermal-hydraulic analysis code for sodium-water reaction developed by Power Reactor and Nuclear Fuel Development Corporation, was improved so as to evaluate the transport of SWRPs in the primary sodium system containing reactor core. In this improvement, SWRPs transport model (REACT), that treats solution, precipitation, deposition and so on, was added and it was intended that REACT is independent of the original part of SWAC-13E as much as possible. The improved analysis code (new SWAC-13E) was applied to the evaluation of SWRPs transport phenomena of typical planned LMFBR plant without secondary sodium system. The results of this analysis were qualitatively reasonable, and it was confirmed that the new SWAC-13E was applicable to the evaluation of the transport behavior of SWRPs.