STUDY ON STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSEL BASED ON THREE-DIMENSIONAL THERMAL-HYDRAULICS AND STRUCTURAL ANALYSES

In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during pressurized thermal shock (PTS) events, the thermal history of the coolant water and the heat transfer coefficient between the coolant water and RPV are dominant factors. These values can be determined on the basis of thermal-hydraulics (TH) analysis simulating PTS events and Jackson-Fewster correlation. Subsequently, using these values, structural integrity assessments of RPV are performed by structural analysis; e.g., loading that affects crack propagation is evaluated. Three-dimensional TH and structural analyses are recommended for precise assessments of the structural integrity of RPV. In this study, we performed TH and structural analyses simulating typical PTS events using three-dimensional models of cold-leg, downcomer and RPV to more accurately assess the structural integrity of RPV. From these analyses, we obtained loading histories from the reactor core region of RPV in which a crack is postulated in the structural integrity assessment. We discuss the conservativeness of current analysis methods on the structural integrity assessment of RPV through the comparison of loading conditions due to PTS events. NOMENCLATURE CCT: continuous cooling transformation Cp: constant pressure specific heat ECCS: emergency core cooling system FEA: finite element analysis Gr: Grashof number H: thermal conducting coefficient LES: large eddy simulation LOCA: loss of coolant accident LSTF: large-scale test facilit