Thermal-hydraulic design and analysis of the steam and water loop facilities to support the development of the EU-demo Tokamak fusion reactor

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dc.contributor.authorVannoni, Alessandra
dc.contributor.editorMašata, David
dc.date.accessioned2025-09-22T08:55:58Z
dc.date.available2025-09-22T08:55:58Z
dc.date.issued2025
dc.description.abstract-translatedThis PhD research supports the development of the EU-DEMO fusion power plant by addressing the thermal-hydraulic challenges related to pulsed operation, especially for the Water-Cooled Lithium-Lead (WCLL) breeding blanket system. A dedicated experimental platform, W-HYDRA, was developed, integrating two complementary facilities: STEAM, for the investigation of a mockup steam generator under pulsed conditions, and the Water Loop, designed to test components under a wide range of thermal-hydraulic conditions. The main objective was the conceptual design and assessment of the steam generator test section based on the Once-Through Steam Generator (OTSG) configuration, chosen for its low thermal inertia and proven reliability in fission applications. Thermal-hydraulic analyses using the RELAP5 code supported the experimental campaign definition and control strategy development. The design of the STEAM facility ensured adequate power dynamics and included safety-oriented evaluations of key components such as air coolers and low-pressure heat exchangers. The Water Loop was designed to test multiple component configurations, including plasma-facing units, by enabling precise control of operating conditions. Sensitivity analyses helped optimize the integration between STEAM and Water Loop, minimizing component redundancy and facility costs. While STEAM focuses on component-level performance validation under pulsed conditions, the Water Loop allows system-level assessments, including transient and safety analyses. The project culminated in the definition of experimental activities and the preparation of technical specifications for component procurement. This work significantly contributes to the qualification of fusion reactor components, providing a unique infrastructure to validate technologies for ITER and DEMO.en
dc.format2 s.cs
dc.identifier.isbn978-80-261-1307-2
dc.identifier.isbn978-80-261-1308-9 (printed)
dc.identifier.urihttp://hdl.handle.net/11025/62832
dc.language.isoenen
dc.publisherUniversity of West Bohemia in Pilsenen
dc.rights© University of West Bohemia in Pilsenen
dc.rights.accessopenAccessen
dc.subjectpostercs
dc.subject.translatedposteren
dc.titleThermal-hydraulic design and analysis of the steam and water loop facilities to support the development of the EU-demo Tokamak fusion reactoren
dc.typekonferenční příspěvekcs
dc.typeconferenceObjecten
dc.type.statusPeer revieweden
local.files.count2*
local.files.size1535401*
local.has.filesyes*

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