Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO

"The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in a demonstration nuclear fusion reactor (DEMO). The choice of He as fuid coolant for the BB is motivated by a virtually complete transparency...

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Autor principal: Caspari, Felix
Otros Autores: Boccaccini, Lorenzo V.
Formato: Tesis de maestría
Lenguaje:Inglés
Publicado: 2018
Materias:
REACTORES NUCLEARES
TERMOHIDRAULICA
FUSION NUCLEAR
DIOXIDO DE CARBONO
FLUIDOS
Acceso en línea:http://ri.itba.edu.ar/handle/123456789/1158
Aporte de:
Repositorio Institucional Instituto Tecnológico de Buenos Aires (ITBA) de Instituto Tecnológico de Buenos Aires (ITBA)
id I32-R138-123456789-1158
record_format dspace
spelling I32-R138-123456789-11582022-12-07T15:20:34Z Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO Caspari, Felix Boccaccini, Lorenzo V. Hernández González, Francisco A. Smoglie, Cecilia REACTORES NUCLEARES TERMOHIDRAULICA FUSION NUCLEAR DIOXIDO DE CARBONO FLUIDOS "The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in a demonstration nuclear fusion reactor (DEMO). The choice of He as fuid coolant for the BB is motivated by a virtually complete transparency to neutrons, leaving unafected the T production capabilities of the blanket, as well as chemical inertness, molecular stability under high temperatures and neutron irradiation and a superior heat conductivity and capacity, leading to the best cooling performance in terms of heat transfer capabilities among other gas cooling choices. However, this cooling performance figure is hindered by the very low density of the gas, which leads to large pressure drops and high pumping power, thus afecting the overall plant efficiency, as well as to chronic leakages and large coolant inventories. These disadvantages, together with the still immature technology readiness of the respective turbomachinery, the price of this coolant, as well as its recognized limited resources pose concerns about the use of He as coolant for a BB in DEMO. On the other side, carbon dioxide has been the fuid coolant choice since the 50's in the nuclear fission industry for gas cooled reactors (MAGNOX, AGR). Despite its lower heat capacity and thermal conductivity (about 22% and 17% of that of helium respectively), its larger density (11 times larger molecular weight for CO2) can lead to an advantageous performance on heat dissipation rate per unit of pumping power. This feature, coupled with its relative transparency to neutrons, the molecular stability at the operating temperatures of the BB and the industrial scale ready turbomachinery makes CO2 an attractive alternative to He. The feasibility of a CO2-cooled breeding blanket is assessed in this work from the point of view of the thermohydraulic performance." Tesis Energía y Ambiente (maestría) - Instituto Tecnológico de Buenos Aires, Buenos Aires - Karlsruher Institut für Technologie, Karlsruhe, 2017 2018-03-26T19:57:07Z 2018-03-26T19:57:07Z 2017 Tesis de maestría http://ri.itba.edu.ar/handle/123456789/1158 en 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 Inglés
topic REACTORES NUCLEARES
TERMOHIDRAULICA
FUSION NUCLEAR
DIOXIDO DE CARBONO
FLUIDOS
spellingShingle REACTORES NUCLEARES
TERMOHIDRAULICA
FUSION NUCLEAR
DIOXIDO DE CARBONO
FLUIDOS
Caspari, Felix
Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
topic_facet REACTORES NUCLEARES
TERMOHIDRAULICA
FUSION NUCLEAR
DIOXIDO DE CARBONO
FLUIDOS
description "The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in a demonstration nuclear fusion reactor (DEMO). The choice of He as fuid coolant for the BB is motivated by a virtually complete transparency to neutrons, leaving unafected the T production capabilities of the blanket, as well as chemical inertness, molecular stability under high temperatures and neutron irradiation and a superior heat conductivity and capacity, leading to the best cooling performance in terms of heat transfer capabilities among other gas cooling choices. However, this cooling performance figure is hindered by the very low density of the gas, which leads to large pressure drops and high pumping power, thus afecting the overall plant efficiency, as well as to chronic leakages and large coolant inventories. These disadvantages, together with the still immature technology readiness of the respective turbomachinery, the price of this coolant, as well as its recognized limited resources pose concerns about the use of He as coolant for a BB in DEMO. On the other side, carbon dioxide has been the fuid coolant choice since the 50's in the nuclear fission industry for gas cooled reactors (MAGNOX, AGR). Despite its lower heat capacity and thermal conductivity (about 22% and 17% of that of helium respectively), its larger density (11 times larger molecular weight for CO2) can lead to an advantageous performance on heat dissipation rate per unit of pumping power. This feature, coupled with its relative transparency to neutrons, the molecular stability at the operating temperatures of the BB and the industrial scale ready turbomachinery makes CO2 an attractive alternative to He. The feasibility of a CO2-cooled breeding blanket is assessed in this work from the point of view of the thermohydraulic performance."
author2 Boccaccini, Lorenzo V.
author_facet Boccaccini, Lorenzo V.
Caspari, Felix
format Tesis de maestría
author Caspari, Felix
author_sort Caspari, Felix
title Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
title_short Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
title_full Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
title_fullStr Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
title_full_unstemmed Thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for DEMO
title_sort thermohydraulic investigation on the use of carbon dioxide as coolant for a solid breeding blanket for demo
publishDate 2018
url http://ri.itba.edu.ar/handle/123456789/1158
work_keys_str_mv AT casparifelix thermohydraulicinvestigationontheuseofcarbondioxideascoolantforasolidbreedingblanketfordemo
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