Development of Three-Dimensional Thermal-Hydraulic Analysis Code for Supercritical Water-Cooled Reactor

摘要

In Japan, development of a supercritical water-cooled nuclear reactor (SCWR) is carried out as one of the next- generation nuclear energy systems as proposed also by GIF (Generation IV International Forum). JAEA (Japan Atomic Energy Agency) is developing the thermal design procedure on two-phase flow thermal- hydraulics of light water-cooled reactors from the former. JAEA has succeeded in the three-dimensional simulations of two-phase flow pattern from the liquid water at the fuel channel inlet to the water-vapor mixture at the outlet inside the reactor core. The obtained results regarding temperature, pressure, velocity and void fraction in the reactor core were clarified quantitatively and reflected to the thermal design study of the advanced light water-cooled reactor [1].