Design and Analysis of a Reactor Pressure Vessel for High Temperature Application

"The following Master’s Thesis deals with the topic of the design and analysis of a reactor pressure vessel for a nuclear reactor concept meant for a high temperature application. This work finds itself within the workframe of a super critical pressurized water reactor (SPWR). The aim of the SP...

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Autor principal: Fernandez, Alvaro Juan
Formato: Disposición
Lenguaje:Español
Publicado: 2026
Materias:
REACTOR PRESSURE VESSEL, NUCLEAR REACTOR, SUPERCRITICAL PRESSURIZED WATER REACTOR, HIGH TEMPERATURE APPLICATION
RECIPIENTE A PRESIÓN DE REACTOR, REACTOR NUCLEAR, REACTOR DE AGUA PRESURIZADA SUPERCRÍTICA, APLICACIONES DE ALTA TEMPERATURA
Acceso en línea:https://hdl.handle.net/20.500.14769/5284
Aporte de:
Repositorio Institucional Instituto Tecnológico de Buenos Aires (ITBA) de Instituto Tecnológico de Buenos Aires (ITBA)
id I32-R138-20.500.14769-5284
record_format dspace
spelling I32-R138-20.500.14769-52842026-03-20T07:33:39Z Design and Analysis of a Reactor Pressure Vessel for High Temperature Application Fernandez, Alvaro Juan REACTOR PRESSURE VESSEL, NUCLEAR REACTOR, SUPERCRITICAL PRESSURIZED WATER REACTOR, HIGH TEMPERATURE APPLICATION RECIPIENTE A PRESIÓN DE REACTOR, REACTOR NUCLEAR, REACTOR DE AGUA PRESURIZADA SUPERCRÍTICA, APLICACIONES DE ALTA TEMPERATURA "The following Master’s Thesis deals with the topic of the design and analysis of a reactor pressure vessel for a nuclear reactor concept meant for a high temperature application. This work finds itself within the workframe of a super critical pressurized water reactor (SPWR). The aim of the SPWR is to achieve an increase in efficiency by increasing the pressure and temperature in the primary loop in order to produce steam at higher temperature in the secondary loop. The scope of the present work is the design and dimensioning of the reactor pressure vessel in accordance with the KTA 3201.2 standard. The RPV was then modelled using CAD software and exported to a FEM software in order to perform the stress analysis. The purpose of this is to determine the viability of the model by examining if the simulated stresses exceed the limitations imposed by the standard for the different loading cases. The stress analysis chapter includes both a static structural analysis, as well as a transient analysis with thermal loadings. Finally, the possible future steps for the development of the RPV are discussed, as well as the possible challenges and improvement opportunities". 2026-03-19T14:16:23Z 2026-03-19T14:16:23Z 2024-02-23 Disposición https://hdl.handle.net/20.500.14769/5284 es application/pdf
institution Instituto Tecnológico de Buenos Aires (ITBA)
institution_str I-32
repository_str R-138
collection Repositorio Institucional Instituto Tecnológico de Buenos Aires (ITBA)
language Español
topic REACTOR PRESSURE VESSEL, NUCLEAR REACTOR, SUPERCRITICAL PRESSURIZED WATER REACTOR, HIGH TEMPERATURE APPLICATION
RECIPIENTE A PRESIÓN DE REACTOR, REACTOR NUCLEAR, REACTOR DE AGUA PRESURIZADA SUPERCRÍTICA, APLICACIONES DE ALTA TEMPERATURA
spellingShingle REACTOR PRESSURE VESSEL, NUCLEAR REACTOR, SUPERCRITICAL PRESSURIZED WATER REACTOR, HIGH TEMPERATURE APPLICATION
RECIPIENTE A PRESIÓN DE REACTOR, REACTOR NUCLEAR, REACTOR DE AGUA PRESURIZADA SUPERCRÍTICA, APLICACIONES DE ALTA TEMPERATURA
Fernandez, Alvaro Juan
Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
topic_facet REACTOR PRESSURE VESSEL, NUCLEAR REACTOR, SUPERCRITICAL PRESSURIZED WATER REACTOR, HIGH TEMPERATURE APPLICATION
RECIPIENTE A PRESIÓN DE REACTOR, REACTOR NUCLEAR, REACTOR DE AGUA PRESURIZADA SUPERCRÍTICA, APLICACIONES DE ALTA TEMPERATURA
description "The following Master’s Thesis deals with the topic of the design and analysis of a reactor pressure vessel for a nuclear reactor concept meant for a high temperature application. This work finds itself within the workframe of a super critical pressurized water reactor (SPWR). The aim of the SPWR is to achieve an increase in efficiency by increasing the pressure and temperature in the primary loop in order to produce steam at higher temperature in the secondary loop. The scope of the present work is the design and dimensioning of the reactor pressure vessel in accordance with the KTA 3201.2 standard. The RPV was then modelled using CAD software and exported to a FEM software in order to perform the stress analysis. The purpose of this is to determine the viability of the model by examining if the simulated stresses exceed the limitations imposed by the standard for the different loading cases. The stress analysis chapter includes both a static structural analysis, as well as a transient analysis with thermal loadings. Finally, the possible future steps for the development of the RPV are discussed, as well as the possible challenges and improvement opportunities".
format Disposición
author Fernandez, Alvaro Juan
author_facet Fernandez, Alvaro Juan
author_sort Fernandez, Alvaro Juan
title Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
title_short Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
title_full Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
title_fullStr Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
title_full_unstemmed Design and Analysis of a Reactor Pressure Vessel for High Temperature Application
title_sort design and analysis of a reactor pressure vessel for high temperature application
publishDate 2026
url https://hdl.handle.net/20.500.14769/5284
work_keys_str_mv AT fernandezalvarojuan designandanalysisofareactorpressurevesselforhightemperatureapplication
_version_ 1865139555239198720

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