Risk Analysis of an interfacing system LOCA in a generic Westinghouse PWR
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Inclou dades d'ús des de 2022
Cita com:
hdl:2117/81016
Tutor / directorAlonso, José Ignacio
Tipus de documentProjecte Final de Màster Oficial
Data2014
Condicions d'accésAccés obert
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continguts d'aquesta obra estan subjectes a la llicència de Creative Commons
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Reconeixement-NoComercial-SenseObraDerivada 3.0 Espanya
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.
MatèriesNuclear 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
TitulacióMÀSTER UNIVERSITARI EN ENGINYERIA NUCLEAR (Pla 2012)
Localització
Col·leccions
Fitxers | Descripció | Mida | Format | Visualitza |
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JeanBaptiste_REPORT_TFM.pdf | Report | 1,447Mb | Visualitza/Obre |