dc.contributor
Alonso, José Ignacio
dc.contributor.author
Favre, Jean-Baptiste
dc.identifier
https://hdl.handle.net/2117/81016
dc.description.abstract
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.
dc.format
application/pdf
dc.publisher
Universitat Politècnica de Catalunya
dc.publisher
École supérieure d'électricité
dc.rights
http://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.rights
Attribution-NonCommercial-NoDerivs 3.0 Spain
dc.subject
Àrees temàtiques de la UPC::Energies::Energia nuclear::Seguretat nuclear
dc.subject
Nuclear reactors -- Safety measures
dc.subject
Nuclear reactors -- Cooling
dc.subject
Nuclear power plants -- Accidents -- Risk assessment
dc.subject
Reactors nuclears -- Mesures de seguretat
dc.subject
Reactors nuclears -- Refrigeració
dc.subject
Reactors nuclears -- Accidents -- Avaluació del risc
dc.title
Risk Analysis of an interfacing system LOCA in a generic Westinghouse PWR
dc.coverage
east=0.8316193000000567; north=41.0194958; name=43891 Vandellòs, Tarragona, Espanya