Risk Analysis of an interfacing system LOCA in a generic Westinghouse PWR
This project has been developed during my internship in the field of Probabilistic Safety Assessment (PSA) in the offices of Westinghouse. These are in the enclosure of Vandellòs’ Nuclear Plant in Hospitalet de l'Infant. The goal of my internship was the modelling and computation of the frequen...
| Autor: | |
|---|---|
| Tipo de recurso: | tesis de maestría |
| Fecha de publicación: | 2014 |
| País: | España |
| Institución: | Universitat Politècnica de Catalunya (UPC) |
| Repositorio: | UPCommons. Portal del coneixement obert de la UPC |
| Idioma: | inglés |
| OAI Identifier: | oai:upcommons.upc.edu:2117/81016 |
| Acceso en línea: | https://hdl.handle.net/2117/81016 |
| Access Level: | acceso abierto |
| Palabra clave: | Nuclear reactors -- Safety measures Nuclear reactors -- Cooling Nuclear power plants -- Accidents -- Risk assessment Reactors nuclears -- Mesures de seguretat Reactors nuclears -- Refrigeració Reactors nuclears -- Accidents -- Avaluació del risc Àrees temàtiques de la UPC::Energies::Energia nuclear::Seguretat nuclear |
| Sumario: | This project has been developed during my internship in the field of Probabilistic Safety Assessment (PSA) in the offices of Westinghouse. These are in the enclosure of Vandellòs’ Nuclear Plant in Hospitalet de l'Infant. The goal of my internship was the modelling and computation of the frequency that an Interfacing System Loss of Coolant Accident (ISLOCA) occurs in the nuclear power plants of Vandellòs and Ascó. In order to achieve this goal, I applied a method to calculate ISLOCA risk frequency (WCAP-17154-P) proposed in august 2013 by Westinghouse, to the nuclear plants of Ascó and Vandellòs. The objective of this report is to illustrate realistically the procedure followed during the internship in order to assess the ISLOCA risk frequency. Considering that all information necessary to perform these assessments for the plants is strictly confidential, the illustration of the procedure will be done over a generic Westingouse PWR three loop reactor, using generic data publicly available or proprietary of Westinghouse. |
|---|