Without a system to counteract the different sources of variability, the plasma in the ITER Tokamak would cease to produce power. Fortunately, scientists can take what has been learned in the discipline of control engineering—principles and techniques that keep a fighter jet in the air—and apply that same know-how to design the robust plasma control system required by ITER. "With the development of driverless cars and control systems for airplanes, the control community has put a lot of thought into controlling critical systems in a holistic and robust way that didn't exist ten or twenty years ago," says Tim Luce.   Two years ago, ITER brought in Luce to head the Science & Operations Department. A physicist with 37 years experience working with fusion, he heads the department responsible for both the software and the hardware of ITER's plasma control system. "Now, with advances in computer and communications technologies, we have the capacity to apply new principles and techniques in real time and not just in an offline, theoretical sense," says Luce.   In the past, most systems had simple input and simple output. But control problems have become more complex, requiring a new generation of algorithms that model much more than just a set of independent sensors and actuators. Changes in one component affect the behaviour of other components. Not only do the new systems have to model the dependencies among the different components, but they also have to model the system as a whole.   Because of this interplay among the different inputs and among the different outputs, the matrix models that work so well for control of single-input and single-output (SISO) systems cannot be applied to the control of a fusion reactor, a multiple-input and multiple-output (MIMO) system. Furthermore, to overcome delays in both measurement times and reaction times, the control system has to employ feedforward methods in addition to the more traditional feedback loops.   A multidimensional control problem and a multitude of unknowns   A fundamental part of the control, data access and communication (CODAC) system, ITER's plasma control system is responsible for ensuring that each pulse is executed correctly. It does this by taking data from sensors and applying sophisticated algorithms to generate commands that it sends to actuators to control plasma parameters, such as position, shape or stability.   "We're starting from a point where we do have experience," says Alberto Loarte, head of the Science Division. "If we compare smaller tokamaks operating at highest power and current to large tokamaks operating at lowest power and current, they run the same. So other than a little tuning, we expect our initial models to be based on the behaviour of known systems such as the JET and JT-60SA tokamaks, which have half the linear dimensions of ITER."   "As we move beyond the first stages of operation, we will get into areas where there are more unknowns," says Loarte. "Running our models through simulations, we've found that sometimes when you apply an actuator and expect a certain reaction, the result turns out to be the opposite of what you expected. That's because of the interplay of other factors that are specific to ITER fusion-power-producing plasmas. It's as if you pressed on the accelerator with your foot, and instead of accelerating, the car stops."   There is still a lot to learn about system behaviour at later stages of operation, when fusion reactions in the plasma will cause the plasma to self-heat. In these later stages, the control system will apply heat to the plasma, thereby causing fusion—and the fusion will produce heat, thereby raising the temperature of the plasma even more. The relationship between external heat and plasma temperature will no longer be direct, as it is in present tokamak experiments. This makes the job of the plasma control system much more complicated.   The stakes are high. Once fusion starts to heat the plasma, if the system fails to adjust exactly as required, the plasma can get too hot for fusion to be efficiently produced. The plasma can even become unstable, causing the plant to stop producing power.   Peter de Vries, Scientific Coordinator in the Stability & Control Section led by Joe Snipes, compares the problem to playing mini golf and trying to putt the ball up to a hole on top of a mound. "If you apply too much force you go over the hole and down the other side of the mound. If you apply too little force, the ball doesn't reach the top of the mound and rolls back down. This analogy gives you an idea of how delicate it is for the plasma control system to adjust the external heat."   Temperature and density are major concerns—and so is the shape of the plasma, which also determines the behaviour of the reactor. To monitor plasma shape, the tokamak contains hundreds of tiny sensors, which measure the magnetic fields at different locations. All that information is fed into the control system, which then models the plasma shape, and compares that with a reference.   "It might find that the plasma wants to bulge out a little here," says de Vries. "So then it calculates what voltages it needs to put on the power supplies to change the currents in all the coils that we have around the machine to push the plasma back into shape. Hundreds of measurements go into a complicated calculation—and out of it go dozens of response requests to make sure everything is kept in the right place, with the right plasma density and temperature."   Future-proofing ITER's plasma control system   Employing some of the latest advances in control engineering, ITER's plasma control system is architected to handle both the basic control functions for early commissioning and the advanced control functions that will be needed for future high performance operation. In preparation for each stage of operation, new functions will be added and existing functions will be adapted to new types of plasmas. All modifications will be integrated into the existing system.   In May 2019 the design team reached the halfway point for the final design of the plasma control system for First Plasma operation, the first fully integrated use of all basic tokamak functions. Halfway through scheduled project duration, many of the controllers have been designed and the framework in which the controllers will work is nearly completed.   As for the next steps, Peter de Vries says, "After this summer we will begin several months of intensive assessment—testing and correcting—and documentation of the design. If all goes well, we should be finished with system design for First Plasma by this time next year."   As holistic and robust control engineering is essential to sustained nuclear fusion, any milestone in the design of the plasma control system is a step forward for ITER.

A Titan's hug is a slow affair. For the sector sub-assembly tools, rotating both arms from "full open" to "full close" will require no less than four hours of near-imperceptible motion. In the Assembly Hall everything is being readied for the tool load tests, which are scheduled to begin in mid-July and last for about one month.   Two 350-tonne test loads, each representing an ITER toroidal field coil, have been assembled on the floor at the entrance. Made of seven different steel-and-concrete modules, the dummies slightly exceed the weight of the actual coils but closely reproduce their centre of gravity and distribution of mass.   During the tests, the mock toroidal field loads will be mounted on the arms of the giant tools and delicately rotated inward to the point where—if they were the real components—they would be close enough to be assembled to the vacuum vessel sector positioned in the centre of the tool, as well as to thermal shield panels.   During the machine assembly phase, this "slow embrace" will be performed nine times—one for each sector of the doughnut-shaped vacuum vessel.   "The weight of the components and the very high accuracy required create very severe conditions," says Ryutaro Okugawa, the leader of the ITER Tooling & Engineering Group, which is overseeing the load test preparation.   First, the stiffness and rigidity of the seven-module loads needs to be confirmed. This will be achieved by lifting the dummies a few centimetres above the shop floor and measuring the stress on the tension bars—the so-called "Macalloys"—that keep the module together.   Then comes the hard part: each load will be lifted and upended using a 800-tonne mobile crane (during the actual assembly activities, a bespoke "upending tool" will be used) working in close coordination with the overhead cranes of the  Assembly Hall.   The mock loads will then be positioned with utmost precision on their dedicated supports within each tool in turn and attached to their respective upper and lower adjustment units.   For the 22-metre-high Titan undergoing testing, it will be time to slowly close its heavily loaded arms and practice—for the first time—the actual embrace of a 440-tonne vacuum vessel sector.

In advance of the June G20 Summit in Osaka, Japan, Prime Minister Shinzo Abe and French President Emmanuel Macron held bilateral talks that resulted in the release of a five-year cooperation plan. Notably, ITER was one of the items on the agenda. The plan provides a roadmap for partnership in the fields of maritime security, infrastructure development, global trade, space, cyberspace, cultural and scientific exchange, and the environment. In Chapter IV (page 5-6), the two countries pledge to reinforce economic partnership with a particular emphasis on innovation—including ways of transitioning to energy systems that are low-carbon or carbon-neutral, affordable and stable. ITER makes that list, as well as the European-Japanese activities of the Broader Approach (advanced fusion energy research taking place in Japan). Download the roadmap in Japanese or French

The table turns slowly as strips of composite material are wound into a perfect ring. One hundred sixty-four turns later, the 3.4-tonne component, with an internal diameter of 5 metres, is ready for bonding, compression, curing, dry machining, inspection and testing. These are ITER's pre-compression rings, a set of nine composite rings that will support the toroidal field magnet superstructure in the face of huge electromagnetic forces during operation. Encircling the tips of the coil structures at top and bottom, two sets of three rings will "push back" with a centripetal force of thousands of tonnes, suppressing any coil deflection and greatly reducing cyclic fatigue stresses. The European Domestic Agency is working with principal contractor CNIM (Toulon, France) for the procurement of nine pre-compression rings (six, plus three spares). The raw material—pultrude laminate—is being procured by the European agency from the Finnish company Exel, while the equipment for last-phase testing was built under an ITER Organization contract awarded to Douce Hydro (France) in collaboration with CNIM.  Production techniques and processes were validated during lengthy prototyping and qualification phases, and series production is underway now. Visit the European Domestic Agency website to see a video of the production process.