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A comparative assessment study for a generation of the pressure-temperature (P-T) limitcurve of a reactor vesel is performed in accordance with ASME code. Using cooling or heating rate andvessel material properties, stress distribution is obtained to calculate stress intensity factors, which arecompared with the material fracture toughness to determine the relations between operating pressure andtemperature during reactor cool-down and heat-up. P-T limit curves are analyzed with respect to defectorientation, clad thickness, toughness curve, cooling or heating rate and neutron fluence. The resulting P-Tcurves are compared each other.