Experimental study of curved guide tubes for pellet injection
Abstract
The use of curved guide tubes for transporting frozen hydrogen pellets offers great flexibility for pellet injection into plasma devices. While this technique has been previously employed, an increased interest in its applicability has been generated with the recent ASDEX Upgrade experimental data for magnetic high-field side (HFS) pellet injection. In these innovative experiments, the pellet penetration appeared to be significantly deeper than for the standard magnetic low-field side injection scheme, along with corresponding greater fueling efficiencies. Thus, some of the major experimental fusion devices are planning experiments with HFS pellet injection. Because of the complex geometries of experimental fusion devices, installations with multiple curved guide tube sections will be required for HFS pellet injection. To more thoroughly understand and document the capability of curved guide tubes, an experimental study is under way at the Oak Ridge National Laboratory (ORNL). In particular, configurations and pellet parameters applicable for the DIII-D tokamak and the International Thermonuclear Experimental Reactor (ITER) were simulated in laboratory experiments. Initial test results with nominal 2.7- and 10-mm-diam deuterium pellets are presented and discussed.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Energy Research, Washington, DC (United States)
- OSTI Identifier:
- 554870
- Report Number(s):
- ORNL/CP-95078; CONF-971065-
ON: DE98000801; BR: AT601020D; TRN: 98:008895
- DOE Contract Number:
- AC05-96OR22464
- Resource Type:
- Technical Report
- Resource Relation:
- Conference: 17. IEEE/NPSS symposium on fusion engineering, San Diego, CA (United States), 6-10 Oct 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION; PELLET INJECTION; GUIDE TUBES; TOKAMAK DEVICES; THERMONUCLEAR REACTOR FUELING; FUEL FEEDING SYSTEMS; ASDEX TOKAMAK; DOUBLET-3 DEVICE; ITER TOKAMAK; EXPERIMENTAL DATA
Citation Formats
Combs, S K, Baylor, L R, Foust, C R, Gouge, M J, Jernigan, T C, and Milora, S L. Experimental study of curved guide tubes for pellet injection. United States: N. p., 1997.
Web. doi:10.2172/554870.
Combs, S K, Baylor, L R, Foust, C R, Gouge, M J, Jernigan, T C, & Milora, S L. Experimental study of curved guide tubes for pellet injection. United States. https://doi.org/10.2172/554870
Combs, S K, Baylor, L R, Foust, C R, Gouge, M J, Jernigan, T C, and Milora, S L. 1997.
"Experimental study of curved guide tubes for pellet injection". United States. https://doi.org/10.2172/554870. https://www.osti.gov/servlets/purl/554870.
@article{osti_554870,
title = {Experimental study of curved guide tubes for pellet injection},
author = {Combs, S K and Baylor, L R and Foust, C R and Gouge, M J and Jernigan, T C and Milora, S L},
abstractNote = {The use of curved guide tubes for transporting frozen hydrogen pellets offers great flexibility for pellet injection into plasma devices. While this technique has been previously employed, an increased interest in its applicability has been generated with the recent ASDEX Upgrade experimental data for magnetic high-field side (HFS) pellet injection. In these innovative experiments, the pellet penetration appeared to be significantly deeper than for the standard magnetic low-field side injection scheme, along with corresponding greater fueling efficiencies. Thus, some of the major experimental fusion devices are planning experiments with HFS pellet injection. Because of the complex geometries of experimental fusion devices, installations with multiple curved guide tube sections will be required for HFS pellet injection. To more thoroughly understand and document the capability of curved guide tubes, an experimental study is under way at the Oak Ridge National Laboratory (ORNL). In particular, configurations and pellet parameters applicable for the DIII-D tokamak and the International Thermonuclear Experimental Reactor (ITER) were simulated in laboratory experiments. Initial test results with nominal 2.7- and 10-mm-diam deuterium pellets are presented and discussed.},
doi = {10.2172/554870},
url = {https://www.osti.gov/biblio/554870},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Dec 01 00:00:00 EST 1997},
month = {Mon Dec 01 00:00:00 EST 1997}
}