Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules
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DOI: 10.1016/j.fusengdes.2016.12.040
Abstract: Abstract The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the framework of the European “Horizon 2020” innovation and research program. One of the key components in the fusion reactor… read more here.
Keywords: helium cooled; rcc mrx; demo; first wall ... See more keywords
Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette
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DOI: 10.1016/j.fusengdes.2017.02.013
Abstract: Abstract One of the fundamental input parameters required for the thermo hydraulic and structural design of a divertor cassette is the operation temperature range. In the current design activities to develop European DEMO divertor in… read more here.
Keywords: temperature; demo; divertor cassette; divertor ... See more keywords
Identification of accident sequences for the DEMO plant
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DOI: 10.1016/j.fusengdes.2017.02.026
Abstract: Abstract Safety studies are performed in the frame of the conceptual design studies for the European Demonstration Fusion Power Plant (DEMO) to assess the safety and environmental impact of design options. An exhaustive set of… read more here.
Keywords: accident sequences; plant; demo; safety ... See more keywords
Parametric explorative study of DEMO galleries pressurization in case of ex-vessel LOCA
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DOI: 10.1016/j.fusengdes.2017.03.120
Abstract: Abstract Radioactive toxins confinement is a main safety function for fusion power plants, hence the importance of confinement design parameters optimization. Moving from this perspective, two Loss of Coolant Accidents (LOCAs) were analyzed: loss of… read more here.
Keywords: parametric explorative; galleries pressurization; demo; loca ... See more keywords
Methodology of the source term estimation for DEMO reactor
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DOI: 10.1016/j.fusengdes.2017.04.101
Abstract: Abstract The problem of source term qualification is one of the most important topics in order to predict possible releases of the Activation Products (APs) and Tritium from the DEMO Fusion reactor. The prevention of… read more here.
Keywords: methodology; source; demo; source term ... See more keywords
Myth of initial loading tritium for DEMO—Modelling of fuel system and operation scenario
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DOI: 10.1016/j.fusengdes.2017.05.138
Abstract: Abstract Any fusion power reactors such as “DEMO” that achieves tritium self-sufficiency with breeding blankets can produce tritium by DD reaction followed by exponential breeding in the blanket within reasonable total operation period. The present… read more here.
Keywords: loading tritium; initial loading; tritium; demo ... See more keywords
Conceptual studies of gamma ray diagnostics for DEMO control
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DOI: 10.1016/j.fusengdes.2018.05.041
Abstract: Abstract The future tokamak demonstration fusion reactor (DEMO) will operate at unprecedented physical and technological conditions where high reliability of the system components is required. The conceptual study of a suite of DEMO diagnostics is… read more here.
Keywords: conceptual studies; demo control; demo; gamma ray ... See more keywords
Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
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DOI: 10.1016/j.fusengdes.2018.05.072
Abstract: Abstract The European DEMOnstration (DEMO) reactor precedes the development of the fully commercial fusion power plant. One of the key components of the DEMO is the first wall (FW). The FW is acted upon by… read more here.
Keywords: water; stress analysis; demo; demo first ... See more keywords
Vacuum vessel Upper Port design assessment of the European DEMO
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DOI: 10.1016/j.fusengdes.2018.10.018
Abstract: Abstract The present work focuses on the design assessment of the DEMO Upper Port. The size of the upper port is defined by the available space in between the toroidal field coils and the required… read more here.
Keywords: port; design assessment; vacuum vessel; demo ... See more keywords
In-box LOCA accident analysis for the European DEMO water-cooled reactor
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DOI: 10.1016/j.fusengdes.2019.01.066
Abstract: Abstract Transient analyses in a water-cooled fusion DEMO (Demonstration Power Plant) reactor have been performed to support the WCLL (Water-Cooled Lithium Lead) breeding blanket design. In this framework, the Design Basis Accident (DBA) analysis of… read more here.
Keywords: water cooled; water; demo; analysis ... See more keywords
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code
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DOI: 10.1016/j.fusengdes.2019.02.021
Abstract: Abstract The conceptual design of the Primary Heat Transfer System (PHTS) of the water-cooled European (EU) DEMO foresees two independent cooling circuits, the breeding zone PHTS and the first wall PHTS. During the pulse time… read more here.
Keywords: water cooled; system; demo; code ... See more keywords