M. Utili , A. Cucchiaro , P. Fusco , M. De Santis , A. Iaboni , P. Meller , M. Micheletti , N. Paganucci , A. Pizzuto , G.M. Polli
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引用次数: 0
Abstract
The primary water cooling system of Divertor Tokamak Test (DTT) facility consists of the circuit which directly cool down the plasma face components of the tokamak, the Inner, TOP and Outboard First Wall and Divertor modules. The systems have been designed in order to handle the maximum plasma heating power of 32.2MW from the First Wall and 30MW for the Divertor modules for 100 s and to perform the baking of the FW and DIV modules. The FW Water Coolant System (WCS) is constituted by the pumping system, heat exchanger storage tanks placed in the auxiliary building (building 174) and pipe lines, pressuriser, instrumentation and valves, placed in the torus hall (building 185). The FW-WCS can manage the total mass flow rate of 381kg/s at 60 °C in five lines: Inner standard and limiter FW; Top FW and Outboard FW Port 2 and Port 3. During the Light Baking the system will be operated at 130 °C and 200 °C during the Strong Baking. Instead, the Divertor WCS is able to manage the total mass flow rate of 577kg/s for the 54 standard divertor modules.
The WCSs have been designed and integrated in the vacuum vessel, cryostat and torus hall taking into account the requirements of the Remote Handling System and diagnostics.
The paper describes the thermo-fluid dynamic design of the FW and DIV primary Water Cooling Systems, the sizing of main components and pipes network and the integration inside DTT facility. The P&ID and 3D modeling in torus hall are presented.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.