Abstract
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.
| Original language | English |
|---|---|
| Article number | 086015 |
| Journal | Nuclear Fusion |
| Volume | 65 |
| Issue number | 8 |
| DOIs | |
| State | Published - Aug 2025 |
Funding
Valuable conversations with Drs. P.C. de Vries and M. Schneider, of the ITER Organization, motivating the pursuit of this study in it early stages, are gratefully acknowledged. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 - EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union (EU) or the European Commission (EC). Neither the EU nor the EC can be held responsible for them. This work has been part-funded by the EPSRC Energy Programme [Grant Number EP/W006839/1]. This work has been funded in part by the US Department of Energy (DOE), under Contract DE-AC05-00OR22725 with UT-Battelle, LLC. Valuable conversations with Drs. P.C. de Vries and M. Schneider, of the ITER Organization, motivating the pursuit of this study in it early stages, are gratefully acknowledged. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 – EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union (EU) or the European Commission (EC). Neither the EU nor the EC can be held responsible for them. This work has been part-funded by the EPSRC Energy Programme [Grant Number EP/W006839/1]. This work has been funded in part by the US Department of Energy (DOE), under Contract DE-AC05-00OR22725 with UT-Battelle, LLC.
Keywords
- ITER
- deuterium-tritium plasmas
- diagnostic residual gas analyzer (DRGA)
- fusion fuel cycle
- fusion plasma control
- joint-European torus (JET)
- magnetic confinement plasmas