DTT, Divertor Tokamak Test facility, is one of the largest nuclear fusion facility under construction in Europe after ITER. Its mission is to provide an integrated nuclear fusion environment where to test power exhaust strategies useful for the first nuclear fusion power plant. It is a fully superconducting tokamak capable of confining deuterium plasmas with high flexibility with respect to shaping and strike point sweeping. Maximum plasma current of Ip = 5.5 MA and toroidal magnetic field of 6 T at the plasma center makes DTT in a position relevant for the present DEMO design. In late 2019, a consortium has been established with the aim at translating the theoretical and technological knowledge of the partners in the design, in the construction and subsequent experimental management and implementation of the Divertor Tokamak Test machine. To the DTT consortium have finally adhered ten partners representing the leading laboratories and universities involved in nuclear fusion in Italy, and the largest Italian oil company. One of the first activities concerned the development and start-up of the project coordination structure. Subsequently the Integrated Project Team started the engineering design phase with the aim at keeping the maturity of the different DTT systems and components so to guarantee the respect of the challenging schedule of construction. This effort led the DTT team to the completion of the design of the systems in critical path in late 2021 and hence to the start of procurement activities. The paper reports the main resulting final design and technical solutions for the systems of the tokamak area whose procurement activities have started or are about to start, and gives an overview of the forthcoming activities.

Status of design and procurement activities in DTT tokamak project area

Dalla Palma M;Valisa M
2022

Abstract

DTT, Divertor Tokamak Test facility, is one of the largest nuclear fusion facility under construction in Europe after ITER. Its mission is to provide an integrated nuclear fusion environment where to test power exhaust strategies useful for the first nuclear fusion power plant. It is a fully superconducting tokamak capable of confining deuterium plasmas with high flexibility with respect to shaping and strike point sweeping. Maximum plasma current of Ip = 5.5 MA and toroidal magnetic field of 6 T at the plasma center makes DTT in a position relevant for the present DEMO design. In late 2019, a consortium has been established with the aim at translating the theoretical and technological knowledge of the partners in the design, in the construction and subsequent experimental management and implementation of the Divertor Tokamak Test machine. To the DTT consortium have finally adhered ten partners representing the leading laboratories and universities involved in nuclear fusion in Italy, and the largest Italian oil company. One of the first activities concerned the development and start-up of the project coordination structure. Subsequently the Integrated Project Team started the engineering design phase with the aim at keeping the maturity of the different DTT systems and components so to guarantee the respect of the challenging schedule of construction. This effort led the DTT team to the completion of the design of the systems in critical path in late 2021 and hence to the start of procurement activities. The paper reports the main resulting final design and technical solutions for the systems of the tokamak area whose procurement activities have started or are about to start, and gives an overview of the forthcoming activities.
2022
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
978-1-6654-4280-0
DTT
nuclear fusion
superconductivity
power supply
divertor
additional heating
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/443552
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