Study On Neutron Characters And Neutronic-Thermohydraulic Coupling Effect In SCWR

The supercritical-pressure Light Water Cooled Reactor (SCWR) is selected by the Generation IV International Forum (GIF) as one of the six Generation IV nuclear systems and emphasis study objects, with characters of simple structure,high thermal efficiency, Which uses supercritical-pressure light water as coolant. Physical properties of water change seriously in pseudo-critical area and cause strong neutronic-thermohydraulic coupling effect in the reactor core. DRAGON is used with neutron diffuse equations to study physical character of reactor core. Single channel thermohydraulic model is developed and heat transfer characters of supercritical water is discussed with grey theory. Assambly model of SCWR is analyzed with neutronic-thermolhydraulic procedure. Results meet design rules of SCWR and provide a theory basic to the safety analysis of SCWR.