Rview of pellet fueling

Milora, S.L.

doi:10.1007/bf01050447

Cited by 116 publications

(69 citation statements)

References 55 publications

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“…1 Neutron emission measured by a plastic scintillator during deuterium pellet injection into an ohmically heated TFTR plasma (a) and into a plasma heated by deuterium neutral beams (b). The H~ signal is used to monitor pellet ablation [9]. The pellet penetrated about 60 cm in the ohmically heated plasma and 44 cm in the beam-heated plasma (the plasma minor radius was a = 81 cm).…”

Section: Experimental Observations and Interpretationmentioning

confidence: 99%

Energetic ion diagnostics using neutron flux measurements during pellet injection

Heidbrink¹

1986

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Neutron measurements during injection of deuterium pellets into deuterium plasmas on the tokamak fusion test reactor (TFTR) indicate that the fractional increase in neutron emission about 0.5 ms after pellet injection is proportional to the fraction of beam-plasma reactions to total fusion reactions in the unperturbed plasma. These observations suggest three diagnostic applications of neutron measurements during pellet injection: (1) measurement of the beam-plasma reaction rate in deuterium plasmas for use in determining the fusion Q in an equivalent deuterium-tritium plasma, (2) measurement of the radial profile of energetic beam ions by varying the pellet size and velocity, and (3) measurement of the "temperature" of ions accelerated during wave heating.

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Section: Experimental Observations and Interpretationmentioning

confidence: 99%

Energetic ion diagnostics using neutron flux measurements during pellet injection

Heidbrink¹

1986

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“…The process and benefits of plasma fueling by the injection of frozen pellets composed of hydrogen isotopes into magnetically confined plasmas have been thoroughly documented in the literature [1,2]. Also, pellet injection has often been exploited as a diagnostic (for instance, to study particle transport and to provide pellets for impurity experiments).…”

Section: Introductionmentioning

confidence: 99%

A new four-barrel pellet injection system for the TJ-II stellarator

Combs

Foust

McGill

et al. 2011

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

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A new pellet injection system for the T J-II stellarator has been developed/constructed as part of a collaboration between the Oak Ridge National Laboratory (ORNL) and the Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT). ORNL is providing most of the injector hardware and instrumentation, the pellet diagnostics, and the pellet transport tubes; ClEM AT is responsible for the injector stand/interface to the stellarator, cryogenic refrigerator, vacuum pumps/ballast volumes, gas manifolds, remote operations, plasma diagnostics, and data acquisition. The pellet injector design is an upgraded version of that used for the ORNL injector installed on the Madison Symmetric Torus (MST). It is a four-barrel system equipped with a cryogenic refrigerator for in situ hydrogen pellet formation and a combined mechanical punch/propellant valve system for pellet acceleration (speeds -100 to 1000 m/s). On T J-II, it will be used as an active diagnostic and for fueling. To accommodate the plasma experiments planned for T J-II, pellet sizes significantly smaller than those typically used for the MST application are required. The system will initially be equipped with four different pellet sizes, with the gun barrel bores ranging between -0.5 to 1.0 mm. The new system is almost complete and is described briefly here, highlighting the new features added since the original MST injector was constructed. Also, the future installation on TJ-I1 is reviewed.

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“…The goals of the TPOP-11 program are (1) to determine the feasibility and conditions under which tritium and D-T mixtures can be extruded, (2) to determine the mechanical and thermal properties of tritium and D-T extrusions, (3) to extrude and accelerate ITER relevant pellets in a repeating mode, (4) to evaluate options for recycling extruder and pellet exhaust, and (5) to evaluate the RPI design in an environment with significant tritium inventory, secondary containment, and interfaces with other tritium processing systems. used a single-stage light gas gun in which single 4-mm-diam pellets were formed in-situ in the barrel and accelerated with high-pressure gas.…”

Section: Tritium Extruder Technologymentioning

confidence: 99%

Development of pellet injection systems for ITER

Combs

Gouge

Baylor

et al.

Proceedings of 16th International Symposium on Fusion Engineering

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7he wbmned nmnusupr has b~e n authored bv a contractor of the U.S. G0Ver-t under contract No DE-Government retams a n o n e x w . ABSTRACTOak Ridge National Laboratory (ORNL) has been developing innovative pellet injection systems for plasma fueliig experiments on magnetic fusion confinement devices for about 20 years. Recently, the ORNL development has focused on meeting the complex fueling needs of the International Thermonuclear Experimental Reactor (ITER). In this paper, we describe the ongoing research and development activities that will lead to a ITER prototype pellet injector test stand. The present effort addresses three main areas: (1) an improved pellet feed and delivery system for centrifuge injectors, (2) a long-pulse (up to steady-state) hydrogen extruder system, and (3) tritium extruder technology. The final prototype system must be fully tritium compatible and will be used to demonstrate the operating parameters and the reliability required for the ITER fueling application.

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Rview of pellet fueling

Cited by 116 publications

References 55 publications

Energetic ion diagnostics using neutron flux measurements during pellet injection

Energetic ion diagnostics using neutron flux measurements during pellet injection

A new four-barrel pellet injection system for the TJ-II stellarator

Development of pellet injection systems for ITER

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