J. Buckerfield , R. Pearce , A. Cobalt , F. Chitu , M. Dremel , J.D. Dupuy , L. Mora , A. Rousseau , J. Benet , G. Kouzmenko , S. Manfrin , A. Rome , A.S. Guichou
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引用次数: 0
Abstract
A custom designed, open structure cryopump provides the required vacuum conditions for the MITICA experiment (Megavolt ITER Injector and Concept Advancement), a full-scale mockup of the ITER Heating Neutral Beam Injector located at the ITER Neutral Beam Test Facility (NBTF) in Padova, Italy. Upon connection to the cryoplant it will become the largest operating Neutral Beam cryopump in the world, designed to achieve the required pumping speeds of 4500 m3/s for H2 and 3600 m3/s for D2 operation. This paper presents the as-built design and manufacture of the pump, outlining the detailed design of each sub-system and the manufacture, assembly and testing processes that led to its successful delivery.
The MITICA cryopump consists of a pair of panels, each 8 m long, 3 m tall and weighing approximately 4 tons. These are comprised of a stainless steel frame supporting 32 pumping sections that are connected together to form two continuous cryogenic circuits, one operated at 4.5 K for cryosorption, the other at 80 K for thermal radiation shielding. Novel manufacturing techniques were developed for the individual cryopanels, including bespoke hydraulic expansion and charcoal coating processes to achieve the required cryopumping performance.
The delivery of the MITICA cryopump is a significant milestone in the development of the ITER Neutral Beam cryopumps, with the lessons learned during manufacture already being implemented in the ongoing design work. This paper therefore not only looks forward to the installation and commissioning of the delivered pump with the MITICA cryoplant but also beyond, towards the future procurement of similar cryopumps that will be installed on the ITER Heating and Diagnostic Neutral Beam Injectors.
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.