Appropriate disposal of the non-neutronic energy and particle exhaust in a reactor is universally recognized as one of the high priority challenges for the exploitation of fusion as an energy source. The new Divertor Tokamak Test (DTT) facility, which will be built in Italy, is a tool to address that challenge in high-field, high performance tokamak with complete integration between core and edge plasma scenarios. The DTT plasma condition will be relevant for DEMO (the european DEMOstration power plant) with condition of power flow to the divertor of 15 MW/m, where 17 MW/m is the expected level for a reactor. DTT is a superconducting tokamak with 6 T of on-axis maximum toroidal magnetic field carrying plasma current up to 5.5 MA, in pulses with length up to 100s. The D-shaped device is up- down symmetric, with major radius R=2.14 m, minor radius a=0.64 m and an average triangularity of 0.3.The auxiliary heating power, coupled to the plasma at maximum performance, is 45 MW, shared between ECH (Electron Cyclotron Heating, ICH (Ion Cyclotron Heating) and NNBI (Negative Neutral Beam Injectors). Many aspects relevant for the physics of magnetic fusion will be addressed. Fast particles up to 700 KeV (simulating the alfa generated by nuclear fusion reaction) will be generated through the ICH power while the chosen energy of NNBI (400 KeV) allows to have a super-Alfvenic population to study fast particle collective transport. A strong relevance will be given also the physics of plasma heating in different scheme and configuration, having DTT the possibility to use all the three main heating systems used in ITER and foreseen in DEMO. The physics of the divertor will be addressed exploiting the possibilities to use DTT as a test bed of new divertor materials (including liquid metals), while preliminary electromagnetic studies confirm the possibility of producing a variety of divertor magnetic topologies. This presentation will discuss the state of the art of the project, illustrating its scientific background, the expected plasma scenarios - in particular as far as plasma exhaust is concerned - and the main technology choices so far. Emphasis will be given to highlight the effort to design an experimental tool, which will be a device not only for plasma exhaust studies, but also for the advancement of fusion science in the grand sense.

Scientific Objectives of the Divertor Tokamak Test (DTT) Facility

Granucci Gustavo
2019

Abstract

Appropriate disposal of the non-neutronic energy and particle exhaust in a reactor is universally recognized as one of the high priority challenges for the exploitation of fusion as an energy source. The new Divertor Tokamak Test (DTT) facility, which will be built in Italy, is a tool to address that challenge in high-field, high performance tokamak with complete integration between core and edge plasma scenarios. The DTT plasma condition will be relevant for DEMO (the european DEMOstration power plant) with condition of power flow to the divertor of 15 MW/m, where 17 MW/m is the expected level for a reactor. DTT is a superconducting tokamak with 6 T of on-axis maximum toroidal magnetic field carrying plasma current up to 5.5 MA, in pulses with length up to 100s. The D-shaped device is up- down symmetric, with major radius R=2.14 m, minor radius a=0.64 m and an average triangularity of 0.3.The auxiliary heating power, coupled to the plasma at maximum performance, is 45 MW, shared between ECH (Electron Cyclotron Heating, ICH (Ion Cyclotron Heating) and NNBI (Negative Neutral Beam Injectors). Many aspects relevant for the physics of magnetic fusion will be addressed. Fast particles up to 700 KeV (simulating the alfa generated by nuclear fusion reaction) will be generated through the ICH power while the chosen energy of NNBI (400 KeV) allows to have a super-Alfvenic population to study fast particle collective transport. A strong relevance will be given also the physics of plasma heating in different scheme and configuration, having DTT the possibility to use all the three main heating systems used in ITER and foreseen in DEMO. The physics of the divertor will be addressed exploiting the possibilities to use DTT as a test bed of new divertor materials (including liquid metals), while preliminary electromagnetic studies confirm the possibility of producing a variety of divertor magnetic topologies. This presentation will discuss the state of the art of the project, illustrating its scientific background, the expected plasma scenarios - in particular as far as plasma exhaust is concerned - and the main technology choices so far. Emphasis will be given to highlight the effort to design an experimental tool, which will be a device not only for plasma exhaust studies, but also for the advancement of fusion science in the grand sense.
2019
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
DTT
Div
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/463429
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