SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety Original Research Article

When the water level in the reactor pressure vessel (RPV) of a pressurized water reactor (PWR) is low enough and the core temperature is such that the coolant in that region boils, reflux-condensation conditions are established. Under such conditions, almost boron-free water is collected in a region of the primary system forming a non-borated slug. If subsequent natural circulation is established or a reactor coolant pump (RCP) is restarted, the slug could be transported to the core. This scenario configures an important part of the so-called boron issue. The Energy Systems Analysis Group at the Institute of Energy Technologies (INTE) of the Technical University of Catalonia (UPC) has studied the boron issue in three different stages. The steps were the following: participation in OECD-related projects, code improvement and investigation at nuclear power plant (NPP) scenarios. The third step is the main aim of this paper and consists of a continuation of the previous projects in the field of NPP analysis. The aim of this paper is to study SBLOCA transients with boron dilution in PWR. The chosen NPP was Ascó-2 which is a 3-loop-2940,6 MWth Westinghouse PWR. The paper contains some references to OECD/SETH and OECD/PKL experimental projects and analyses an established scenario including features of boron transport and sensitivity calculations for relevant parameters.