High-Speed Repetitive Pellet Injector Prototype for Magnetic Confinement Fusion Devices

Frattolillo, A.; Gasparotto, M.; Migliori, S.; Angelone, G.; Baldarelli, M.; Scaramuzzi, F.; Ronci, G.; Combs, S. K.; Milora, S.L.; Foust, C. R.; Gouge, M.J.; Reggiori, A.; Riva, G.; Carlevaro, R.; Daminelli, Giambattista

doi:10.1016/b978-0-444-89995-8.50093-x

Cited by 5 publications

(1 citation statement)

References 4 publications

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“…In the early 90's a long lasting collaboration between ENEA and Oak Ridge National Laboratory (ORNL), concerning the development of high-speed pellet injectors, was started, with the initial aim of developing the first repeating high-speed device. A facility was assembled at ORNL, combining an existing ORNL piston extruder and an ENEA repeating TSG [13], [14]. Sequences of up to 20 solid D2 pellets (limited by the capacity of the extruder reservoir) were launched with a repetition rate of up to  1 Hz and speeds up to  2.5 km/s [15], [16], [17], [18].…”

Section: The Enea-ornl High-speed Pellet Injectormentioning

confidence: 99%

Core Fueling of DEMO by Direct Line Injection of High-Speed Pellets From the HFS

Frattolillo

Baylor

Bombarda

et al. 2018

IEEE Trans. Plasma Sci.

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Pellet injection represents to date the most realistic candidate technology for core fueling of a DEMO tokamak fusion reactor. Modelling of both pellet penetration and fuel deposition profiles, for different injection locations, indicates that effective core fuelling can be achieved launching pellets from the inboard high field side at speeds not less than 1 km/s. Inboard pellet fueling is commonly achieved in present tokamaks, using curved guide tubes; however, this technology might be hampered at velocities  1 km/s. An innovative approach, aimed at identifying suitable inboard "direct line" paths, to inject high-speed pellets (in the 3 to 4 km/s range), has been recently proposed as a potential complementary solution. The fuel deposition profiles achievable by this approach have been explored using the HPI2 simulation code. The results presented here show that there are possible geometrical schemes providing good fueling performance. The problem of neutron flux in a direct line of sight injection path is being investigated, though preliminary analyses indicate that, perhaps, this is not a serious problem. The identification and integration of straight injection paths suitably tilted may be a rather difficult task, due to the many constraints and to interference with existing structures. The suitability of straight guide tubes to reduce the scatter cone of high-speed pellets, is therefore of main interest. A preliminary investigation,, aimed at addressing these technological issues, has been recently started. A possible implementation plan, using an existing ENEA-ORNL facility is shortly outlined. Index Terms-DEMO tokamak fusion reactor, HFS highspeed pellet injection, straight guide tubes Manuscript received June 2017. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

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