ºÚÁÏÉçapp

The elements of the ºÚÁÏÉçapp divertor that will directly face the hot plasma must withstand a heat load that is estimated at ten times that of a spacecraft re-entering Earth's atmosphere.

Procuring parties Russia (divertor dome), Japan (divertor outer targets) and Europe (divertor inner targets) are all engaged in multiyear qualification programs that include prototype fabrication and high heat flux testing.

The European Domestic Agency made the choice of contracting with three separate manufacturers for the development of small-scale inner vertical target prototypes that are 1/19th of the actual scale needed for ºÚÁÏÉçapp. In the first stage of the pre-qualification program the prototypes were successfully tested in high heat flux conditions; the next step will now be to develop full-scale prototypes. This phase¡ªwhich involves the three manufacturers plus a fourth, pre-qualified supplier¡ªis expected to last approximately three years.

Read the full article on the European Domestic Agency .

We have learned with profound sadness of the passing of Dr Yasuo Shimomura, who served as ºÚÁÏÉçapp Deputy Director from the beginning of the Engineering Design Activities (EDA) in 1992 until 2001. From 2001 until 2003 Dr Shimomura was ºÚÁÏÉçapp International Team Co-Leader, and from 2003 until 2005 he was ºÚÁÏÉçapp Interim Project Leader; during this last period he led the ºÚÁÏÉçapp team through the difficult transitional phase from the design activity to the start of construction in 2006.

A graduate of Osaka University, Dr Shimomura had a distinguished career in fusion research at the Japan Atomic Energy Research Institute, JAERI (now part of the National Institutes for Quantum and Radiological Science and Technology, QST). He was a leading figure in the construction and operation of the JFT-2a/DIVA tokamak, developing a reactor-relevant divertor concept that is currently being applied to ºÚÁÏÉçapp. He was also Leader of the JT-60 Experimental Planning and Analysis Group, and in 1986 was appointed as Head of the Large Tokamak Experiment Division at JAERI, with overall responsibility for the JT-60 tokamak. From 1988 he combined the leadership of the JT-60 device and its conversion to JT-60U with an appointment as Head of the Poloidal Field Design Group within the ºÚÁÏÉçapp Conceptual Design Activities (CDA). He was appointed ºÚÁÏÉçapp Deputy Director within the ºÚÁÏÉçapp EDA in July 1992, with responsibility for the design integration of the project. Dr Shimomura also held guest scientist positions at Princeton Plasma Physics Laboratory from 1976 to 1977 and at the Max-Planck-Institut f¨¹r Plasmaphysik in Garching from 1981 to 1982.

Dr Shimomura will be remembered by his many friends and colleagues in the ºÚÁÏÉçapp community as a gifted physicist who contributed greatly to the project during an involvement spanning 20 years. He will be greatly missed by all who knew him and who benefitted from his leadership and guidance.

In ºÚÁÏÉçapp, six technological solutions for tritium breeding¡ªin the form of test blanket modules plus associated ancillary systems¡ªwill be operated and tested for the first time. Their experimental validation will represent a major step for fusion development beyond ºÚÁÏÉçapp, when tritium fuel will necessarily have to be bred within the reactor.

In China, Europe, India, Japan and Korea these solutions are under development, with Russia and the United States contributing R&D and providing general support for the test blanket module program.

Europe is developing two types of test blanket modules, which consist of a steel box containing tritium breeders, neutron multiplier materials and heat extraction plates. Over the past two years, the European Domestic Agency and industrial partners have been manufacturing mockups of these boxes to test welding techniques. A preliminary welding procedure, employing a tungsten inert gas (TIG) welding robot to carry out the tasks within the limited space of the box, has been identified. The welding qualification cycle is expected to end within the next two years.

See the full article on the European Domestic Agency .

Edmund Synakowski¡ªthe Associate Director of the US Department of Energy (DOE) Office of Fusion Energy Sciences and former ºÚÁÏÉçapp Council Vice-Chair¡ªhas been chosen as the University of Wyoming's vice president for research and economic development. Synakowski will also be a professor in the university's Department of Physics and Astronomy.

The role of the vice president for research and economic development is to support and facilitate the research efforts of University of Wyoming's faculty, staff and students; direct the university's research mission as a public research university; promote the university's research program with stakeholders; and direct technology transfer and commercialization efforts for the university's intellectual property.

Synakowski has held his current position, associate director of science in the Department of Energy, since 2009, administering a budget of about $400 million annually to develop nuclear fusion as an energy source. His agency supports research at more than 50 universities, eight national and two federal laboratories, and 15 industry groups.

He previously led the Fusion Energy Program at the Lawrence Livermore National Laboratory in California and held a number of roles at Princeton University's Plasma Physics Laboratory.

Read the full report on the University of Wyoming's website .

At least 100 miniature cameras will be installed inside the ºÚÁÏÉçapp machine to act as the eyes for operators charged with machine maintenance.

Some of them will give a wide-angle view of the inside of the machine; others will be embedded on the robotic arms used for repairs. By receiving live image from the cameras, engineers hundreds of metres away will be able to operate maintenance and repair equipment with extreme accuracy.

The European Domestic Agency has been working with Oxford Technologies Limited (OTL) to develop and validate the different subsystems of the miniature cameras, which will have to operate within severe space constraints and often in an environment exposed to radiation. Subsystems developed by ISAE, France (image sensors); CEA, France (illumination system); and Jean Monnet University Saint Etienne, France (optic system) have been successfully tested over the past year at Belgium's SCK-CEN facility where they were exposed to different levels of gamma radiation.

The next step will be to develop a camera prototype.

Read the full story on the European Domestic Agency .

To predict the impact of removing exhaust heat from the ºÚÁÏÉçapp Tokamak, researchers are calling on the Titan supercomputer at the Oak Ridge Leadership Computing Facility in the US.

Using the 27-petaflop behemoth, researchers based at Princeton Plasma Physics Laboratory (PPPL) are simulating the area where the plasma edge meets the divertor¡ªthe material structure engineered to remove exhaust heat from the vacuum vessel. Specifically, the team has evaluated the heat-flux width at the divertor, or the width of the material surface that might sustain the highest heat load.

Because the divertor directly faces the exhaust flow, it is bombarded with hot particles driven by electromagnetic fluctuations. In ºÚÁÏÉçapp, in order to withstand the highest surface heat load, the divertor will be made of the toughest element on Earth: tungsten.

"You don't want to start and stop ºÚÁÏÉçapp too often to replace this divertor material, so it has to be able to withstand the heat load," team leader C.S. Chang reports. "Ideally, we want the hot exhaust particles to hit the surface in a much wider area so that it's not damaged."

Based on simulations made possible by Titan's supercomputing capacity, Chang's team predicts that in ºÚÁÏÉçapp, due to the size of the plasma, edge plasma turbulence may spread heat across a larger area of the divertor surface and significantly increase the heat-flux width relative to current smaller-scale fusion devices.

Read the full report on research results at .

At the Swiss Plasma Center in Lausanne, Switzerland, the TCV tokamak was recently shut down for an upgrade of its Thomson scattering diagnostic. The operation was successful: shortly after commissioning the first measurements demonstrated greatly enhanced spatial and spectral resolution for the temperature and density profile measurements of TCV plasmas.

TCV is a variable configuration tokamak with highly specialized capabilities (plasma shaping, versatile electron cyclotron heating, measurement, control systems) for the exploration of the physics of magnetically confined plasmas.

See the full article on the EPFL/Swiss Plasma Center .

Under contract with the European Domestic Agency, a team of experts has been working for more than a year to identify key technologies to perform the cutting and welding operations that will be required during the change-out of ºÚÁÏÉçapp divertor cassettes.

The technical constraints are enormous¡ªthe work (both cutting and welding) will have to be performed remotely, the operational space is severely limited, and no lubricant can be applied as ºÚÁÏÉçapp is a nuclear environment.

Experts from Assystem UK and the UKAEA robotics development laboratory RACE (for Remote Applications in Challenging Environments) have identified candidate techniques; now trials are underway and the search is on for the best tools to do the work remotely.

Read more on the European Domestic Agency .

The steel, the pipes, the tangle of cables and wires ... to sum it looks confusingly technological¡ªbut to others it's inspiring!

UK artist Sarah Moncrieff specialises in urban scenes and industrial interiors. She first heard of JET, the European fusion research experiment hosted at the Culham Centre for Fusion Energy (CCFE), via a friend who works at the site.

"He thought, quite accurately, that I would be interested in it as a subject for my painting. What I hadn't anticipated was how much I would become interested in the work that is done at Culham. The work is fascinating and the sense of seeing something at the forefront of scientific progress was thrilling for me. I know that excitement informed my paintings."

Sarah's paintings of JET were recently exposed at an on-site Open Day, to popular acclaim. You can see more of Sarah's work on her .

Read the full article at .

After celebrating its First Plasma in December 2016, the WEST tokamak (for W Environment in Steady-state Tokamak) was reopened for the installation of two modified LHCD antennas for plasma heating (through lower hybrid current drive), then plasma operations restarted in April 2017.

Although plasma breakdown was routinely achieved, the ramping up of the plasma current was found to be difficult due to induced currents in the passive structures that have been introduced inside the vacuum vessel to produce the divertor configuration.

In effect, the WEST test platform is a modification of the Tore Supra tokamak at the Institute for Magnetic Research (CEA Cadarache, France) that introduces an actively cooled tungsten divertor. The machine has been considerably altered, with a "welcoming structure" for the new divertor, new in-vessel coils, new diagnostics, and adaptations to the heating, fuelling and cooling systems.

The vessel has been reopened to address stray magnetic field compensation through modification of the divertor baffle and a reduction in its electric conductivity to limit induced current. Experiments are expected to resume by the end of June.

Read more in the lastest .

For fusion to generate substantial energy, the ultra-hot plasma that fuels fusion reactions must remain stable and kept from cooling. Researchers have recently shown lithium, a soft, silver-white metal, to be effective in both respects during path-setting US-Chinese experiments on the Experimental Advanced Superconducting Tokamak (EAST) in Hefei, China.

Seven US researchers traveled to EAST in December, 2016, to participate in the experiments. They deployed lithium in the Chinese tokamak in three different ways: through a lithium powder injector, a lithium granule injector, and a flowing liquid lithium limiter (FLiLi) that delivered the element in liquid form to the edge of EAST plasmas. Good results were shown by all three techniques.

Leading the US collaboration is the US Department of Energy's (DOE) Princeton Plasma Physics Laboratory (PPPL), together with co-principal investigators Los Alamos and Oak Ridge National Laboratories, with Johns Hopkins University, the University of Illinois at Urbana-Champaign, the University of Tennessee-Knoxville, and the Massachusetts Institute of Technology. Scientists from General Atomics also participate via a separate grant.

-- John Greenwald, PPPL

See the full report on the PPPL .

It is with great regret that the ºÚÁÏÉçapp community has learned of the sudden passing of Professor Predhiman Krishan Kaw on 18 June.

Professor Kaw was a well-known and highly respected plasma physicist, author of over 380 research publications in scientific journals. He was the founding director of the Institute for Plasma Research in Gujarat, India, which he led from 1986 to 2012. Named Year of Science Chair by the Indian Department of Science & Technology (DST), Professor Kaw continued to be active in research and in the mentoring and training of the younger generation of plasma physicists as DST Professor at the Institute for Plasma Research.

Professor Kaw was also the first Chair of the ºÚÁÏÉçapp Council Science and Technology Advisory Committee (STAC), leading the committee's deliberations from 2007 to 2009, and a regular participant to ºÚÁÏÉçapp Council meetings as Representative of India.

For his outstanding contributions to experimental and/or theoretical research in fundamental plasma physics and plasma applications, he was awarded the prestigious Padma Shri award (India's fourth highest honour) in 1985; the Shanti Swarup Bhatnagar Prize for Science and Technology in 1986; the World Academy of Sciences (TWAP) Prize in 2008; and the Subrahmanyan Chandrasekhar Prize of Plasma Physics in 2016 (see related article in Newsline).

See the Institute for Plasma Research for more information.

Professor Predhiman Krishan Kaw (2nd from left) is seen here on 21 November 2014 at the inauguration of the Cryostat Workshop, where India is assembling the ºÚÁÏÉçapp cryostat. With him are the former ºÚÁÏÉçapp Director-General Osamu Motojima; M.V. Kotwal, president of Larsen & Toubro's Heavy Engineering Division; and Shishir P. Deshpande, Head of the Indian Domestic Agency.

The Culham Centre for Fusion Energy (CCFE) in the UK is looking for people in the fusion community who could benefit from its new cloud-based computing facility, which has a capacity to crunch data that could help researchers and promote collaborative projects. 

The  Modular Data Centre, which opened in May, propels CCFE into the next era of supercomputing. With a total of 1128 cores, 18 terabytes of RAM and 170 TB of high performance storage¡ªand the capacity to grow in sync with CCFE's need for computing power¡ªthe cloud-base system is also open to users across the international fusion community.

Interested parties should contact Rob Akers at @email.

Lithium compounds improve plasma performance in fusion devices just as well as pure lithium does, a team of physicists at the U.S. Department of Energy's (DOE) Princeton Plasma Physics Laboratory (PPPL) has found.

The research was conducted by former Princeton University physics graduate student Matt Lucia under the guidance of Robert Kaita, principal research physicist at PPPL and one of Lucia's thesis advisors, as well as the team of scientists working on a machine known as the Lithium Tokamak Experiment (LTX).

Lucia used a new device known as the materials analysis and particle probe (MAPP), invented at the University of Illinois at Urbana-Champaign and installed on LTX. The MAPP system lets scientists withdraw samples into a chamber connected to LTX and study them without compromising LTX's vacuum environment. MAPP lets scientists analyze how tokamak plasmas affect a material immediately after the experiment ends. In the past, scientists could only study samples after the machine had been shut down for maintenance; at that point, the vacuum had been broken and the samples had been exposed to many experiments, as well as to air.

Lucia used the evaporation technique to coat a piece of metal with lithium, and then used MAPP to expose the metal to plasma within LTX. As he expected, Lucia observed lithium oxide, which forms when lithium reacts with residual oxygen in LTX's vacuum chamber. He was surprised, however, to find that the compound was just as capable of absorbing deuterium as pure lithium was.

"Matt discovered that even after the lithium coating was allowed to sit on the plasma-facing components within LTX and oxidize, it still was able to bind hydrogen," said Kaita.

Lucia's results are the first direct evidence that lithium oxide forms on tokamak walls and that it retains hydrogen isotopes as well as pure lithium does. They support the observation that lithium oxide can form on both graphite, like the tiles in NSTX, and on metal, and improve plasma performance.

Read the full article by Raphael Rosen on the PPPL .

-- Physicists Robert Kaita and Michael Jaworski in front of another PPPL fusion device, the NSTX-Upgrade.

In the context of its to the realization of fusion electricity , the European Consortium for the Development of Fusion Energy, has identified a number of crucial technical challenges that must be addressed through advanced research.

One of these is finding a viable solution for the heat exhaust in a future fusion reactor, considering that the divertor strategy planned for ºÚÁÏÉçapp cannot be extrapolated to a larger, steady-state facility.

Late 2015, EUROfusion called for proposals on plasma exhaust projects, which an independent panel of experts evaluated. The call, termed Plasma Exhaust (PEX) Assessment, received ten proposals that covered conventional and alternative divertors, as well as conventional materials and plasma-facing units as well as advanced materials.

EUROfusion selected six projects for receiving support. These include: ASDEX Upgrade at the Max Planck Institute of Plasma Physics, Garching (Germany); Forschungszentrum J¨¹lich (Germany); Jozef Stefan Institute (Slovenia); MAST-Upgrade, (United Kingdom); TCV at the Swiss Plasma Center (Switzerland); and WEST at CEA (France).

Read the full article at EUROfusion .

--Photo of the JET tokamak courtesy EUROfusion

After the success of the first fusion writers' edition of Fusion in Europe , the magazine is again looking for ambitious volunteer writers for the 2017 autumn issue.

Fusion in Europe is the regular publication of EUROfusion, the European Consortium for the Development of Fusion Energy, which manages European fusion research activitites on behalf of Euratom.

Applicants should be enthusiastic and ambitious, with ideas about how to share the promise of fusion with the world. The deadline is 21 June. For more information, please visit .

Scientists now have a better understanding of the factors leading to steel degradation and of the ways to improve the design and development of key components, such as the ºÚÁÏÉçapp breeding blankets¡ªwhere tritium fuel will be produced from the interaction of fusion neutrons with lithium.

In a unique test facility at the Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA) in Brasimone, candidate steels were exposed to liquid lithium in order to measure degradation (corrosion and/or erosion) over time.

Two types of reduced activation ferritic martensitic (RAFM) steels under consideration for fusion applications¡ªEUROFER97 and F82H¡ªwere tested at ENEA's LiFus6, built for the project (IFMIF will carry out testing and qualification of advanced materials under conditions similar to those of a future fusion power plant/EVEDA is advancing the engineering validation of key IFMIF components and systems).

IFMIF/EVEDA is developed jointly by Europe and Japan in the framework of the agreement, which covers fusion R&D activities that are complementary to ºÚÁÏÉçapp and the next-stage device DEMO.

Read more about the successful LiFus6 test campaign on the European Domestic Agency .

Image: Celebrating at ENEA: IFMIF/EVEDA Project Committee members and representatives of contributing laboratories.

Following an initial run at the Wendelstein 7-X stellarator that lasted from December 2015 to March 2016, a shutdown phase ensued to equip the machine for an operational campaign with longer discharges and higher heating power.

As part of tasks to prepare for the next phase, programmed to start this summer, technicians have installed or adapted 8,000 graphite tiles on the inner wall of the plasma vessel, replaced the limiter with a test divertor, and installed cooling structures such as pipes and shields.

Read about the complexity of these shutdown activities in the latest "."

Image: courtesy of IPP Greifswald

Culham's new tokamak is to receive funding to tackle one of the hottest issues in fusion energy research¡ªplasma exhaust.

, the European consortium for fusion R&D, has approved the first phase of its contribution to a ?21-million program of enhancements to MAST Upgrade, which is only months away from its first operations. Funding for the enhancements, which will be phased from now to 2022, will come jointly from EUROfusion and the UK's Engineering and Physical Sciences Research Council.

The controlled exhaust of power and particles from a very hot tokamak fusion plasma, through the divertor area of the machine, is arguably the biggest challenge facing a future fusion power plant. The extreme power loadings (>10 megawatts per square metre¡ªhigher than that on a spacecraft re-entering Earth's atmosphere) in a conventional divertor will require regular replacement of reactor components and adversely affect the economics and cost of electricity. It is no surprise, then, that divertor and exhaust physics is a major part of EUROfusion's reactor design work as part of their EU to the Realisation of Fusion Energy.

See the at the Culham Centre for Fusion Energy (CCFE) to find out more about the planned enhancements.

Researchers at the U.S. Department of Energy's (DOE) Princeton Plasma Physics Laboratory (PPPL) and General Atomics have simulated a mysterious self-organized flow of the superhot plasma that fuels fusion reactions. The findings show that pumping more heat into the core of the plasma can drive instabilities that create plasma rotation inside the doughnut-shaped tokamak that houses the hot charged gas. This rotation may be used to improve the stability and performance of fusion devices.

The results, reported in January in the journal Physical Review Letters, use first principles-based plasma turbulence simulations of experiments performed on the DIII-D National Fusion Facility that General Atomics operates for the DOE in San Diego. The findings could lead to improved control of fusion reactions in ºÚÁÏÉçapp, the international experiment under construction in France to demonstrate the feasibility of fusion power.

Read the full article on the PPPL .