Abstract
The realization of the Divertor Tokamak Test (DTT) facility is one of the key milestones of the European Roadmap, aiming to explore alternative power exhaust solutions for DEMO, the first nuclear-fusion power plant that will be connected to the European grid. For the actual implementation of the DTT and DEMO plants, it is necessary to define the structure of the internal electric power distribution system, able to supply unconventional loads with a sufficient level of reliability. The present paper reports the preliminary studies for the feasibility and realization of the electrical power systems of DTT, describing the methodology adopted to obtain a first distribution configuration and providing some simulation results. In particular, the first stage of the study deals with the survey and characterization of the electrical loads, which allows defining a general layout of the facility and size the main electrical components. To verify the correctness of the assumptions, simulation models of the grid were implemented in the DIgSILENT PowerFactory software in order to carry out power flow and fault analyses.
Highlights
The Divertor Tokamak Test (DTT) facility is one of the main projects within the framework of the European Roadmap to the realization of fusion energy [1] whose final goal is the development of DEMO [2,3], the first demonstrative power plant able to deliver to an external grid a net electrical energy produced by nuclear-fusion processes
Even though some conventional approaches for the divertor systems will be tested in the international experiment ITER, under construction in France [6], it could be difficult to extrapolate them to the operating conditions expected in DEMO or in a commercial power plant
The present paper describes the preliminary studies to verify the design of the electrical distribution and protection systems of the DTT plant
Summary
The Divertor Tokamak Test (DTT) facility is one of the main projects within the framework of the European Roadmap to the realization of fusion energy [1] whose final goal is the development of DEMO [2,3], the first demonstrative power plant able to deliver to an external grid a net electrical energy produced by nuclear-fusion processes. Even though some conventional approaches for the divertor systems will be tested in the international experiment ITER, under construction in France [6], it could be difficult to extrapolate them to the operating conditions expected in DEMO or in a commercial power plant. For this reason, the DTT facility is a high-performance superconducting tokamak [4] addressed to explore alternative solutions for the power exhaust problem by testing different divertor geometries and materials suitable for DEMO [7].
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