Abstract
Increasing robustness of the ITER diagnostic residual gas analyzer (DRGA) is critical for the potential control of plasma heating and fuel-cycle processing. Robustness is a requirement for a diagnostic to have a control function. The DRGA is a multisensor diagnostic system capable of resolving isotopic compositions of hydrogen and helium as well as other heavier elements and compounds. The divertor-specific DRGA system is intended to measure the composition of gases in the ITER subdivertor region and midplane. Its analysis station will be located in a port cell at the divertor level. From there, it will sample a slip stream of gas from the cryogenic pump duct. It will then exhaust into a shared roughing line where helium or other light gas impurities, some potentially from other diagnostic systems, are likely to be present. In order to provide reliable measurements, the DRGA must be robust in areas such as plasma optical emission source geometry for a compact design, mitigation of back-streaming from light gases and resilience to the ITER port cell environment, and radiation hardening of the DRGA electronics. By incorporating robustness into the design, areas of plasma heating and fuel-cycle control may be explored with the DRGA for ITER and next-generation fusion devices.
| Original language | English |
|---|---|
| Pages (from-to) | 3892-3897 |
| Number of pages | 6 |
| Journal | IEEE Transactions on Plasma Science |
| Volume | 52 |
| Issue number | 9 |
| DOIs | |
| State | Published - 2024 |
Funding
This work was supported by UT-Battelle, Limited Liability Company (LLC), under Contract DE-AC05-00OR22725 with the U.S. Department of Energy (DOE). DRGA WBS lead David Rasmussen for his guidance and use of DRGA fuel cycle figure. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization. The U.S. government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https://energy.gov/downloads/doe-public-access-plan).
Keywords
- Deuterium-tritium plasmas
- Joint European Torus (JET)
- diagnostic residual gas analyzer (DRGA)
- fusion fuel cycle
- mass spectroscopy
- optical spectroscopy
- plasma diagnostics
- radiation hardening
- tokamaks
- tritium (T)
- turbomolecular pumping