TY - JOUR
T1 - Feasibility of fusion plasma burn control via real-time, sub-divertor neutral gas isotopic and compositional analysis
AU - JET Contributors
AU - The EUROfusion Tokamak Exploitation Team
AU - Klepper, C. C.
AU - Lerche, E.
AU - Graber, V.
AU - Delabie, E.
AU - Schuster, E.
AU - Biewer, T. M.
AU - Lore, J. D.
AU - Jacquet, P.
AU - Mantsinen, M. J.
AU - Marcus, C.
AU - Quinlan, B. R.
N1 - Publisher Copyright:
© The Author(s) and UT Battelle. Published by IOP Publishing Ltd on behalf of the IAEA.
PY - 2025/8
Y1 - 2025/8
N2 - The ability to provide fusion burn control without requiring physical access through the first wall and fuel breeding blankets, would be vital for any future, magnetically confined fusion power reactor. A multi-sensor, fusion fuel cycle exhaust, neutral gas analysis system on JET, capable of delivering real time data, and accessing only the sub-divertor region, provides an excellent example of such capability. Optimized for and operated during the deuterium-tritium experimental campaigns 2 and 3 (DTE2, DTE3), it is proving valuable for planning to explore fusion reactor burn control in ITER with a comparable diagnostic system called the Diagnostic Residual Gas Analyzer (DRGA). This paper aims to show feasibility of developing model-based controllers for ITER and next generation, reactor-relevant devices, by building both on the empirical experience in JET-DTE2, and on the already emerging experience on developing such models specifically for ITER. The paper begins with a specific use-case from JET-DTE2, pertaining to the observed sensitivity of the fusion neutron yield on the concentration of isotopic helium-3 (3He), with data from one of the high-performance DT shots exhibited with emphasis on the 3He measurement via the sub-divertor. Then, a first model is developed and then explored with simulations that aim to discover how well the controllers in the model react to either insufficient levels of 3He or excessive levels of 3He. The simulations then explore potential impact from a delay in the measurement (or the response) that would be comparable to the ∼1 s, conductance limited response for the ITER DRGA system, currently in its final design. The simulations show that control is feasible, and that its effectiveness is not significantly impacted by such delay.
AB - The ability to provide fusion burn control without requiring physical access through the first wall and fuel breeding blankets, would be vital for any future, magnetically confined fusion power reactor. A multi-sensor, fusion fuel cycle exhaust, neutral gas analysis system on JET, capable of delivering real time data, and accessing only the sub-divertor region, provides an excellent example of such capability. Optimized for and operated during the deuterium-tritium experimental campaigns 2 and 3 (DTE2, DTE3), it is proving valuable for planning to explore fusion reactor burn control in ITER with a comparable diagnostic system called the Diagnostic Residual Gas Analyzer (DRGA). This paper aims to show feasibility of developing model-based controllers for ITER and next generation, reactor-relevant devices, by building both on the empirical experience in JET-DTE2, and on the already emerging experience on developing such models specifically for ITER. The paper begins with a specific use-case from JET-DTE2, pertaining to the observed sensitivity of the fusion neutron yield on the concentration of isotopic helium-3 (3He), with data from one of the high-performance DT shots exhibited with emphasis on the 3He measurement via the sub-divertor. Then, a first model is developed and then explored with simulations that aim to discover how well the controllers in the model react to either insufficient levels of 3He or excessive levels of 3He. The simulations then explore potential impact from a delay in the measurement (or the response) that would be comparable to the ∼1 s, conductance limited response for the ITER DRGA system, currently in its final design. The simulations show that control is feasible, and that its effectiveness is not significantly impacted by such delay.
KW - ITER
KW - deuterium-tritium plasmas
KW - diagnostic residual gas analyzer (DRGA)
KW - fusion fuel cycle
KW - fusion plasma control
KW - joint-European torus (JET)
KW - magnetic confinement plasmas
UR - https://www.scopus.com/pages/publications/105011709221
U2 - 10.1088/1741-4326/ade9dc
DO - 10.1088/1741-4326/ade9dc
M3 - Article
AN - SCOPUS:105011709221
SN - 0029-5515
VL - 65
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 8
M1 - 086015
ER -