Developments and Challenges in the Design of the ITER DRGA
Abstract
We report the ITER Diagnostic Residual Gas Analyzer (DRGA) will measure the distribution of gas species, i.e., deuterium (D), tritium (T), and impurities, in the divertor exhaust stream and in the plasma periphery, with time resolution relevant to fusion plasma–wall particle dynamics. The uniqueness of the DRGA, over previous implementations of plasma dynamics residual gas analysis, is an integrated approach, combining mass and low-temperature plasma-activated optical spectroscopy, in a differentially pumped analysis station. A further unique feature of the ITER divertor-specific DRGA is an ~8-m separation of the analysis station from the sampled pumping duct, while still maintaining a ~1-s response time for hydrogen isotopic concentrations. ITER DRGA final design activities are strongly benefiting from testing of prototypical DRGA components and methods on present fusion devices, most currently on JET and W7-X. DRGA systems are implemented on both these devices and include sensors (and pumping methods) that are directly relevant to the ITER DRGA design. The recent JET-DTE2 campaign has provided the first experience on operating the combined ITER DRGA sensors with D-T plasmas. While enhancing system design for ITER, this experience on operating devices has also revealed additional engineering challenges, which further guide the continuing final design project. Meanwhile,more »
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
- ITER Organization, St. Paul Lez Durance (France)
- CEA, IRFM, Saint Paul Lez Durance (France)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC); European Union (EU)
- Contributing Org.:
- JET Contributors
- OSTI Identifier:
- 1909138
- Grant/Contract Number:
- AC05-00OR22725; 101052200
- Resource Type:
- Accepted Manuscript
- Journal Name:
- IEEE Transactions on Plasma Science
- Additional Journal Information:
- Journal Volume: 50; Journal Issue: 12; Journal ID: ISSN 0093-3813
- Publisher:
- IEEE
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Deuterium-tritium plasmas; Diagnostic Residual Gas Analyzer (DRGA); fusion fuel cycle; Joint-European Torus (JET); magnetic confinement plasmas; mass spectroscopy; optical spectroscopy; plasma diagnostics; tokamaks; tritium (T)
Citation Formats
Klepper, C. Christopher, Delabie, Ephrem, Jepu, Ionut, Andrew, P., Biewer, Theodore M., Boyd, G. Ted, Douai, David, Hughes, Shaun, Kruezi, Uron, Marcus, Chris, Neilson, G. H., Rasmussen, David A., Ravelli, Fabio A., and Vartanian, Stephane. Developments and Challenges in the Design of the ITER DRGA. United States: N. p., 2022.
Web. doi:10.1109/tps.2022.3223648.
Klepper, C. Christopher, Delabie, Ephrem, Jepu, Ionut, Andrew, P., Biewer, Theodore M., Boyd, G. Ted, Douai, David, Hughes, Shaun, Kruezi, Uron, Marcus, Chris, Neilson, G. H., Rasmussen, David A., Ravelli, Fabio A., & Vartanian, Stephane. Developments and Challenges in the Design of the ITER DRGA. United States. https://doi.org/10.1109/tps.2022.3223648
Klepper, C. Christopher, Delabie, Ephrem, Jepu, Ionut, Andrew, P., Biewer, Theodore M., Boyd, G. Ted, Douai, David, Hughes, Shaun, Kruezi, Uron, Marcus, Chris, Neilson, G. H., Rasmussen, David A., Ravelli, Fabio A., and Vartanian, Stephane. Wed .
"Developments and Challenges in the Design of the ITER DRGA". United States. https://doi.org/10.1109/tps.2022.3223648. https://www.osti.gov/servlets/purl/1909138.
@article{osti_1909138,
title = {Developments and Challenges in the Design of the ITER DRGA},
author = {Klepper, C. Christopher and Delabie, Ephrem and Jepu, Ionut and Andrew, P. and Biewer, Theodore M. and Boyd, G. Ted and Douai, David and Hughes, Shaun and Kruezi, Uron and Marcus, Chris and Neilson, G. H. and Rasmussen, David A. and Ravelli, Fabio A. and Vartanian, Stephane},
abstractNote = {We report the ITER Diagnostic Residual Gas Analyzer (DRGA) will measure the distribution of gas species, i.e., deuterium (D), tritium (T), and impurities, in the divertor exhaust stream and in the plasma periphery, with time resolution relevant to fusion plasma–wall particle dynamics. The uniqueness of the DRGA, over previous implementations of plasma dynamics residual gas analysis, is an integrated approach, combining mass and low-temperature plasma-activated optical spectroscopy, in a differentially pumped analysis station. A further unique feature of the ITER divertor-specific DRGA is an ~8-m separation of the analysis station from the sampled pumping duct, while still maintaining a ~1-s response time for hydrogen isotopic concentrations. ITER DRGA final design activities are strongly benefiting from testing of prototypical DRGA components and methods on present fusion devices, most currently on JET and W7-X. DRGA systems are implemented on both these devices and include sensors (and pumping methods) that are directly relevant to the ITER DRGA design. The recent JET-DTE2 campaign has provided the first experience on operating the combined ITER DRGA sensors with D-T plasmas. While enhancing system design for ITER, this experience on operating devices has also revealed additional engineering challenges, which further guide the continuing final design project. Meanwhile, the recent determination that the ITER DRGA, with slight optimization, will resolve the helium isotopes well enough to support an ITER pre-DT, He-3-based heating scheme, has greatly increased ITER Research Program interest in the DRGA and its implementation well ahead of the DT phase.},
doi = {10.1109/tps.2022.3223648},
journal = {IEEE Transactions on Plasma Science},
number = 12,
volume = 50,
place = {United States},
year = {Wed Dec 14 00:00:00 EST 2022},
month = {Wed Dec 14 00:00:00 EST 2022}
}
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