Vacuum Tight Threaded Junctions (VTTJ): A new solution for reliable heterogeneous junctions in ITER

Agostinetti, Piero; Palma, M. Dalla; Agostini, F. Degli; Marcuzzi, D.; Rizzolo, A.; Rossetto, F.; Sonato, P.; Zaccaria, P.

doi:10.1016/j.fusengdes.2015.04.010

Cited by 6 publications

(2 citation statements)

References 7 publications

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“…R&D activities were performed in support of the design: a novel concept has been developed with regard to heterogeneous joints, resulting in a patent registered as the Vacuum Tight Threaded Junction (VTTJ) technique [16,17], and an Insulation and Cooling Experiment (ICE) testing facility has been established to test the specific small cooling ducts embedded in the thickness of the actively cooled copper components, characterizing single channels and complete parts of grids [18][19][20].…”

Section: Spider Beam Sourcementioning

confidence: 99%

“…The design of the BS was completed in 2015 [43]; some critical parts, such as large ceramic post insulators linking the different stages of the accelerator [62], thick Mo coated surfaces protecting rear vertical plates from heat load and sputtering effects caused by impinging backscattered positive ions [63], customized design of RF lines [64], and heterogeneous joints [16], have required significant R&D to verify the feasibility of manufacturing and to qualify in advance unconventional manufacturing processes.…”

Section: The Mitica Beam Sourcementioning

confidence: 99%

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The PRIMA Test Facility: SPIDER and MITICA test-beds for ITER neutral beam injectors

Toigo¹,

Piovan²,

Bello³

et al. 2017

New J. Phys.

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157

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The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on ITER Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of the ITER heating neutral beam injector, and SPIDER, the full-size radio frequency negative-ions source. The NBTF realization and the exploitation of SPIDER and MITICA have been recognized as necessary to make the future operation of the ITER heating neutral beam injectors efficient and reliable, fundamental to the achievement of thermonuclear-relevant plasma parameters in ITER. This paper reports on design and R&D carried out to construct PRIMA, SPIDER and MITICA, and highlights the huge progress made in just a few years, from the signature of the agreement for the NBTF realization in 2011, up to now-when the buildings and relevant infrastructures have been completed, SPIDER is entering the integrated commissioning phase and the procurements of several MITICA components are at a well advanced stage.

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