Proposal of the confinement strategy of radioactive and hazardous materials for the European DEMO

Jin, Xue Zhou; Carloni, D.; Stieglitz, Robert; Ciattaglia, S.; Johnston, Jane; Nigel, Taylor

doi:10.1088/1741-4326/aa5ee6

Cited by 5 publications

(3 citation statements)

References 3 publications

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“…Preliminary assessments conducted for a DEMO like configuration have identified different sources present in operation but also after plasma shut down. Energy sources are identified such as enthalpy stored in structure and coolant, plasma thermal energy, magnetic energy in coil systems, disruption mechanical energy caused by a plasma collapse in operation; decay heat after a plasma shutdown; energy arising from exothermal chemical reactions between materials, and energy released due to a postulated H 2 explosion [104].…”

Section: Inherent Passive Safety In a Loss-of-coolant (Loca) Eventmentioning

confidence: 99%

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Development of advanced high heat flux and plasma-facing materials

et al. 2017

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Plasma-facing materials and components in a fusion reactor are the interface between the plasma and the material part. The operational conditions in this environment are probably the most challenging parameters for any material: high power loads and large particle and neutron fluxes are simultaneously impinging at their surfaces. To realize fusion in a tokamak or stellarator reactor, given the proven geometries and technological solutions, requires an improvement of the thermo-mechanical capabilities of currently available materials. In its first part this article describes the requirements and needs for new, advanced materials for the plasma-facing components. Starting points are capabilities and limitations of tungsten-based alloys and structurally stabilized materials. Furthermore, material requirements from the fusion-specific loading scenarios of a divertor in a water-cooled configuration are described, defining directions for the material development. Finally, safety requirements for a fusion reactor with its specific accident scenarios and their potential environmental impact lead to the definition of inherently passive materials, avoiding release of radioactive material through intrinsic material properties. The second part of this article demonstrates current material development lines answering the fusion-specific requirements for high heat flux materials. New composite materials, in particular fiber-reinforced and laminated structures, as well as mechanically alloyed tungsten materials, allow the extension of the thermo-mechanical operation space towards regions of extreme steady-state and transient loads. Self-passivating

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Section: Inherent Passive Safety In a Loss-of-coolant (Loca) Eventmentioning

confidence: 99%

“…The aim of a safe plant design is to prevent any off-site emergency measures for the most exposed individual (MEI) outside the plant at any incident conceivable, see figure 10. Regarding the radioactive sources the following contributors have been identified for DEMO [104]:…”

Section: Inherent Passive Safety In a Loss-of-coolant (Loca) Eventmentioning

confidence: 99%

Development of advanced high heat flux and plasma-facing materials

et al. 2017

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“…The second confinement system, aiming at protecting other workers and the members of the public, is the ultimate line of defense against radiological releases. It comprises internal rooms and the tokamak and tritium buildings; moreover, it is equipped with active systems for the purification and detritiation of the building environments [8].…”

Section: Introductionmentioning

confidence: 99%

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

et al. 2023

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The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, the complexity of the plant, and the presence of massive energy sources require a rigorous safety approach to fully realize fusion power’s environmental advantages. The Tokamak building barrier design must address two main issues: radioactive mass transport hazards and energy-related or pressure/vacuum hazards. Safety studies are performed in the frame of the EUROfusion Safety And Environment (SAE) work package to support design improvement and evaluate the thermal-hydraulic behavior of confinement building environments during accident conditions in addition to source term mobilization. This paper focuses on developing a thermal-hydraulic model of the EU-DEMO Tokamak building. A preliminary model of the heat ventilation and air conditioning system and vent detritiation system is developed. A loss-of-coolant accident is studied by investigating the Tokamak building pressurization, source term mobilization, and release. Different nodalizations were compared, highlighting their effects on source term estimation. Results suggest that the building design should be improved to maintain the pressure below safety limits; some mitigative systems are preliminarily investigated for this purpose.

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