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Out now: flying JT-60SA Toroidal Field coils on film

F4E News - wo, 18/04/2018 - 02:00
Our latest clip shows one of the most challenging transports ever contracted by F4E: the air freight of the last two TF coils for JT-60SA.

Plasma physics | Be clean, be strong

ITER - ma, 16/04/2018 - 17:33

To achieve maximum fusion efficiency in a tokamak device it is essential to limit the impurities in the plasma. But this can be a challenge, as interaction between the hot plasma and the material surfaces of the vacuum vessel causes material particles to detach and enter the swirling cloud of gas.
The laws of physics dictate the maximum plasma density that can be achieved for a given current in a tokamak, which means that in ITER—as in other tokamak devices—there will be an upper limit to the number of atoms that can be confined.
Within this limit, it is important that the plasma contain as many atoms as possible that are capable of reacting to produce fusion—in ITER's case, atoms of deuterium and tritium.
Even in trace amounts, other atoms ("impurities") dilute the core of the plasma by taking the space that could be occupied by the fusion fuels, resulting in fewer reactions and a reduction in energy production. And because fusion reactions occur in a roughly proportional manner to the square of fuel density, the "multiplier" effect sets in quickly—fewer fuel atoms result in a dramatic drop-off in fusion reactions, while more fuel results in a rapid increase.
Impurities originate from vacuum vessel and the in-vessel component materials ... iron from the steel components, beryllium from the top layers of the first-wall panels protecting the vacuum vessel, and tungsten from the divertor targets. 
Impurities not only dilute the plasma but—depending on the physical properties of the atoms involved (the number of electrons)—they can also cool it to differing degrees. "The process is similar to that in a fluorescent lamp," explains Alberto Loarte, who leads the Confinement & Modelling Section at ITER. "The electrons of the impurity atoms run into the electrons in the plasma and drain their energy, re-emitting it as electromagnetic radiation—including visible light."
The heavier elements, in particular, drain a lot of energy from the plasma through radiation because of a high number of electrons (tungsten has 74). The energy lost through impurity radiation cools the plasma down and the fusion reactions stop.
In ITER, to keep these radiative losses to a minimum, the divertor will be working from its position at the bottom of the machine to continually exhaust impurities from the plasma and limit contamination.
The very properties that make impurities unwelcome in the core of the plasma, however, can be applied to beneficial effect in the plasma edge region.
Because the energy confinement provided by the machine's magnetic fields is not perfect, large power fluxes can find their way to the edge of the plasma and onto the divertor targets. To avoid localized depositions that would be too high for the material components to withstand, scientists will inject impurity gases at the plasma edge. The radiative properties of the impurities will act to reduce the power fluxes to the material elements by dissipating their energy over a larger zone.
As the plasma in this edge/divertor region is already at temperatures much lower than those required to produce fusion power, this plasma cooling will not affect fusion power production in ITER.

Europe is ready to switch on SPIDER - the most powerful negative ion source experiment to date

F4E News - ma, 16/04/2018 - 02:00
The test bed of the ITER Neutral Beam Test Facility is ready!

The EU Council mandates the Commission to formally approve the new ITER baseline at the next ITER Council

F4E News - ma, 16/04/2018 - 02:00
Europe reaffirms its commitment to the ITER project and to the 2025 target date

Ring coils | Hot resin before the deep cold

ITER - ma, 09/04/2018 - 16:23



It has been almost one year since the fabrication of the first ring coil was launched in the on-site Poloidal Field Coil Winding Facility by European Domestic Agency contractors. Out of the eight "double pancake" conductor windings needed to finalize the 350-tonne magnet, three have been wound and are ready to pass through the resin-impregnation phase—an operation that contributes to both electrical insulation and structural strength.
On one of the circular platforms on the southern end of the silent, clean and temperature-controlled facility, a double pancake sits, still attached by 24 lifting points to the circular spreader beam that has just moved it from the stacking station.
A few metres away, technicians are busy assembling the vacuum containment vessel—the "mould"—that will enclose the double pancakes throughout the lengthy and delicate resin impregnation process.
"During impregnation, we inject some 600 litres of epoxy resin at a temperature of 55-60 °C through entry ports in the mould," explains Gian Battista Fachin of the European Domestic Agency, who works in the facility where Europe is fabricating the four largest ITER poloidal field coils. "At that temperature the resin is as liquid as water and easily penetrates through the fiberglass wrapping of the double pancake."
Once extra pressure has been applied inside the leak-tight mould to insure that all micro spaces are properly filled, the resin's temperature is ramped up first to 100 °C for a few hours of "gelling," then to 140 °C for a full day and a half of "curing." By then, the resin has become rock solid and the shining white double pancake has turned into a massive block the colour of caramel.
The resin impregnation process was tested and validated on a "dummy" conductor winding that is presently stored at the far end of the building.
"We learned a lot from the dummy, right from the beginning operations that began in November 2015," confirms Gian. "We established metrics and procedures, refined bending parameters, impregnation and injection durations ... everything a dummy is for."
The dummy is a perfect replica of an actual double pancake for the 17-metre-in-diameter poloidal field coil #5 (PF5). For reasons of cost however, it is wound from copper conductor rather than from superconducting niobium-titanium alloy.
When all eight double pancakes for PF5 are finalized (winding is underway on the fourth in the series now) they will be stacked to form a winding pack—the coil's very core—which will be wrapped with insulating fiberglass tape and impregnated with resin as one single component.
The winding pack will then receive additional equipment such as clamps, protection covers and pipes. At that point, one last crucial operation remains to be performed before the component can be considered fit for duty.
When ITER enters operation, liquid helium circulating inside the conductor will bring the coil temperature down to 4 K (minus 269 °C) to create the physical conditions for superconductivity in the niobium-titanium conductor.
Throughout the manufacturing process, sample tests and quality control have insured that the conductor's performance in such extreme conditions is in line with the magnet system's requirements.
What remains to be tested however, is the coil's behaviour as a whole. How is it affected by the thermal contractions generated by the ultra-cold temperature? Does the liquid helium circuit within the cable-in-conduit conductor remain leak-tight? Can cracks develop in the resin and hinder electrical insulation?
These questions can be answered without having to cool the coil all the way down to 4 K. At the temperature of liquid nitrogen (80 K or minus 193 °C) thermal contractions have already reached their maximum and all the potential issues can be identified. Also, cooling with liquid nitrogen is much cheaper and easier to implement than cooling with liquid helium.
In May, the cold testing equipment will arrive from Italy for installation in the northern end of the workshop. The four coils manufactured on site (ranging from 17 to 24 metres in diameter) will be tested one after the other in the cold testing vacuum vessel, as will a smaller coil (10 metres in diameter) that is being manufactured in China under an agreement with Europe.
Cold-testing operations are scheduled to begin in the summer of 2019 and last for more than one year.

Object Kinetic Monte Carlo and Finite Element developments for the creation of a Macroscopic Rate Equation model of fusion reactor walls

EFDA - di, 03/04/2018 - 09:14

This 2 years post-doctoral position is offered in the framework of the collaborative project WHeSCI (piim.univ-amu.fr/amidex/whesci), financed by the A*MIDEX foundation (amidex.univ-amu.fr) and proposed in the context of the International Thermonuclear Experimental Reactor (ITER), the international project that aims to demonstrate the technological and scientific feasibility of fusion energy with the Tokamak design (www.iter.org). The WHeSCI project seeks to describe the interactions of the fusion fuel (deuterium (D) and tritium (T)) and ashes (helium (He) and neutron) with the walls of the exhaust of the reactor (the divertor made of Tungsten, W). The induced material properties modifications are indeed critical for the reactor operation and safety and the successful operation of ITER requires a detailed understanding of the plasma-wall interactions.

In this context, the post-doctoral fellow will be involved in the further development of the MHIMS and HIIPC Macroscopic Rate Equation (MRE) models [1-4], which are describing so far the D/T fuel trapping in bulk metals, in absence or in presence of bubbles in the micrometre range. In particular, he/she will study and implement synergistic effects between D/T/He implantations and neutron-induced defects in tungsten materials. Object Kinetic Monte Carlo (OKMC) simulations will be used to obtain a dynamical insight onto temporal and thermal evolution of D/T/He and defects in W. Ultimately, OKMC simulations will provide information on bubble nucleation. The input parameters for the OKMC code LAKIMOCA [5] will come from the literature but also from several WHeSCI project partners: atomic-scale events energies and attempt frequencies will come from DFT calculations, spatial distribution of defects and D/T/He species will come from experiments. Once bubble nucleation is understood, its growth will be investigated with Finite Element Methods (FEM) [6]. Based on this numerical approach, D/T/He trapping and bubble growth will be included in the MRE simulations. This work will be done in close collaboration with a PhD student at CNRS/LSPM who is currently developing the Abaqus Finite Element Method (FEM) code as well as a staff of the CEA group working on the MHIMS program.

The candidate should have a PhD in computational physics, a solid background in solid state physics and show skills in the field of metallic materials. At least one experience of OKMC or FEM simulations is required. As the candidate will have to interact with the various actors in the project, good oral and written communication skills are necessary and the ability to work in a collaborative research environment is essential. Knowledge of French would be appreciated but is not mandatory.

The 1st year of the contract will be located in Lille (France) and will focus on OKMC simulations with Charlotte Becquart (CNRS/UMET – University Lille). The 2nd year will be located in Paris and will focus on FEM and MRE implementations with Yann Charles and Jonathan Mougenot (CNRS/LSPM – University Paris 13). Christian Grisolia (CEA/IRFM) will coordinate the simulation work. The postdoctoral contract is financed by the WHeSCI project (coordinated by Régis Bisson, Aix-Marseille University/PIIM).

Application is open until May 31 and the earliest starting date is July 1 2018. Questions should be sent directly to the following contact persons:

Christian Grisolia christian.grisolia AT cea DOT fr
Laboratoire IRFM – CEA Cadarache – 13115 Saint-Paul-lez-Durance

Charlotte Becquart charlotte.becquart AT univ-lille1 DOT fr
Laboratoire UMET- Université Lille 1 – 59655 Villeneuve d’Ascq

Yann Charles yann.charles AT univ-paris13 DOT fr

Jonathan Mougenot jonathan.mougenot AT univ-paris13 DOT fr
Laboratoire LSPM – Université Paris 13 – 93430 Villetaneuse

Régis Bisson regis.bisson AT univ-amu DOT fr
Laboratoire PIIM – Aix-Marseille University – 13013 Marseille

 

[1] E.A. Hodille et al Nucl. Fusion 57 076019 (2017)

[2] E.A. Hodille et al Phys. Scr. T167 014011 (2016)

[3] C. Sang et al Nucl. Fusion 52 043003 (2012)

[4] C. Quiros et al Nucl. Mat. Ener. 12 1178-1183 (2017)

[5] C.S. Becquart et al. J. Nucl. Mater. 403 75-88 (2010)

[6] Y. Charles et al IJHE 42 20336-350 (2017)

The post Object Kinetic Monte Carlo and Finite Element developments for the creation of a Macroscopic Rate Equation model of fusion reactor walls appeared first on EUROfusion.

The easy JET – European device will move to Berlin

EFDA - zo, 01/04/2018 - 10:36

(The construction site of the BER International airport in Germany from above. It offers not only a lot of space but also state-of-the-art hotels and restaurants as well as a direct fly-in for JET’s scientists. Picture: Creative Commons)

Sources close to the European Commission Directorate Research, Science and Innovation have finally confirmed what used to be only talk behind closed doors. The Joint European Torus (JET), EUROfusion’s flagship and a pioneer experiment of the European Union, will be transferred to the European mainland.
Representatives of the European Commission, the United Kingdom and the German government agreed in Brussels to move the fusion experiment over to Berlin, right into the heart of Europe.

“JET is the most developed fusion experiment in the world. We saw an urgent need to keep the machine, the knowledge and, above all, our 300 international scientists safe”, says a relieved Lorne Horton, JET’s exploitation manager, shortly after the two hours of intense talks.

JET’s Torus Hall Picture: © Copyright protected by United Kingdom Atomic Energy Authority

Before Queen Elizabeth II and François Mitterrand inaugurated The Joint European Torus as a frontier European experiment in 1984, Germany and the United Kingdom fought fiercely to become the host. But in 1977, to Germany’s disappointment, Culham was chosen.

JET is the only machine in the world able to operate the ‘real’ fusion fuel: a mixture of deuterium and tritium. JET has proven this capability in 1997 when its first Deuterium-Tritium (DT) campaign broke the record for the highest amount of fusion power ever produced.

EUROfusion, the European consortium for fusion research, together with the Culham Center for Fusion Energy (CCFE) had originally planned for a second DT campaign in Culham. The preparations and the installation of new diagnostics had been going for years. Since the new set of DT experiments was scheduled for 2019/2020, representatives of EUROfusion lobbied for a new JET site as Britain is supposed to formally break away from continental Europe in 2019.

The German government which did not succeed to host JET in the first run offered now a suitable area. According to our information, the long-delayed Brandenburg airport will definitely not be finalised. Colleagues close to Engelbert Lütke Daldrup, the Head of the BER airport, heard him saying: “Before we tear the whole compound down, we rather make use of it in order to show our support for the European Union.”

Just like the former Culham airfield, JET will get a large base including brand new runways, hotels and restaurants. In fact, EUROfusion’s scientists, who come from 30 different countries in order to carry out experiments at the European tokamak, will undeniably benefit from the well-developed and, above all, modern infrastructure around its new facilities.

Also, the travel expenses could decrease if EUROfusion decides to collaborate with a new industrial partner. The flight company EasyJET had recently announced to expand in Berlin. It is said that EUROfusion’s Programme Manager Tony Donné is currently discussing an irresistible deal with EasyJET’s Chief executive Johan Lundgren about extra low fares for European fusion scientists with destination Berlin: “The name says it all and we should make use of it”, he adds smilingly.

The post The easy JET – European device will move to Berlin appeared first on EUROfusion.

Plant systems | Entering the stage, one by one

ITER - ma, 26/03/2018 - 17:19

As buildings rise out of the earth and equipment is progressively installed, ITER's Science & Operations Department is busy making plans to commission the first plant systems.
Commissioning is the final check that each of the components and plant systems have been designed, manufactured and installed correctly. It is an opportunity to transfer knowledge to the operations team, test all the procedures, and get ready to start the first experiments.
To commission a facility as complicated as ITER it is necessary to proceed in small and gradual steps—checking each part before moving onto the next, and bringing together more and more pieces of the puzzle until the whole facility is working as one. At that point we will be ready to turn on the Tokamak and make plasma.
We will start this year by energizing the electrical distribution systems, since without electricity nothing can work. ITER is directly connected to France's 400 kV public transmission network. Transformers and switchgears located on the ITER platform will "propagate" this power all over the site to provide the correct voltage for each of the clients.
Last year, a test was performed with the first energization of a 400 kV bay, in order to validate all procedures and contractual requirements with French transmission system operator.
Once power is available, the central control system will be turned on and made ready to control, monitor and record data from each of the systems to come. The first task for the control system will then be to start up the cooling water systems and the cooling towers, testing each pump and valve before starting the circulation and flow tests.
_To_134_Tx_With power, control and cooling in place we will begin commissioning the production and distribution networks for various gases and liquids, as well as the air conditioning to remove heat generated by the plant in each building. We then start up the nitrogen and helium production facilities in the cryogenic plant and the various auxiliary vacuum pumping systems.
The specialized Tokamak systems come next—the electron cyclotron system that generates megawatts of microwave energy to heat the plasma, cryogenic pumping systems able to produce ultra-high vacuum, and the power supplies needed to energize the superconducting magnets.
When all of these systems have passed their tests we are ready: the construction phase of ITER is complete and we can start the operations phase with integrated commissioning of all systems working together. All air will be evacuated out of the vacuum vessel and cryostat to bring the pressure inside to one millionth of normal atmospheric pressure; the magnets will be cooled down to -269 °C and energized to create the magnetic confinement field; and a tiny amount of hydrogen gas will be injected and heated up to produce a critical milestone for ITER—First Plasma.
Once this has been achieved we will press on—turning up the current on the magnets to full power and completing their stress testing under all the various field combinations.
At that point we will have shown that the ITER machine is ready for the researchers.

Success for Europe’s equipment that will be used to heat up ITER plasma

F4E News - ma, 26/03/2018 - 02:00
F4E, Ampegon and ITER IO test the first of the Electron Cyclotron power supply units.

Blanket shield blocks | Full-scale prototype passes key test in China

ITER - ma, 19/03/2018 - 16:22


A full-scale prototype of a blanket shield block manufactured in China successfully passed acceptance tests, including the challenging hot helium leak testing in February. An important qualification milestone has been achieved in the ITER blanket program ...

On 14 February, two days before the start of the Chinese New Year, the Chinese Domestic Agency successfully accomplished the last in a series of back-to-back qualification milestones in its program to procure 50 percent of the blanket shield blocks required by ITER.
The ITER blanket consists of 440 individual modules covering a surface of 600 m² inside of the vacuum vessel. The plasma-facing surface of the blanket—the first wall—is attached to massive components called shield blocks that provide neutron shielding for the vessel and magnet coil systems. These thick steel blocks, weighing up to four tonnes apiece, interface with many other systems, in particular a large number of diagnostics. For this reason there are a total of 28 major design variants and 150 or more minor design variants. The Chinese and Korean Domestic Agencies are each providing 220 shield blocks.
In December 2017, Chinese suppliers in Guangzhou completed an 18-month program to manufacture a full-scale prototype of shield block SB09A. The next month, a dedicated facility for hot helium leak testing was commissioned in Chengdu—just in time to begin test activities on the SB09A prototype. From 6 to 14 February, hot helium leak tests were carried out according to ITER Organization accepted procedures, and witnessed by ITER Organization representatives. The results met all relevant ITER requirements.
The shield block module SB09A, located in the upper region inside the vacuum vessel, represents probably the most complex type of shield block structure—making it the most challenging to manufacture of all shield blocks to be procured by China. It has the most complex geometry, with several cut-outs to accommodate interfacing systems and diagnostics, and is largely tapered. For this reason it was selected as a full-scale prototype to qualify the manufacturing technologies that will be used in series production.
Chinese manufacturers started on the full-scale prototype in July 2016, progressively accomplishing all of the fabrication steps including machining datum, drilling the deep holes of the cooling channel, side machining, welding of cover plates, and final machining. From nine tonnes of original stainless steel forgings, the final full-scale prototype after machining was 2.8 tonnes. Many tests were performed throughout the fabrication process to verify quality—such as preliminary dimensional examination, non-destructive examination, and hydraulic pressure tests, which all showed acceptable manufacturing results.
The shield blocks, like all the in-vessel components, have to operate under ultra-high vacuum conditions (ten billion times lower than atmospheric pressure). Therefore stringent design, manufacturing and testing provisions have to be planned in order to ensure that the demanding vacuum requirements are met. In this regard, the so-called hot helium leak test represents the definitive demonstration of the fitness for purpose of the component to operate in an ultra-high vacuum environment. This test foresees the cycling of the components up to the operational temperature and pressure in order to be able to detect the tiniest microleaks, which would not be detectable by other means.
During commissioning tests at the dedicated hot helium leak test facility in Chengdu, operators verified that the sensitivity of the helium detector and the background helium leak rate could reach ITER requirements; in both cases the facility performed well.
During two full cycles of testing on the full-scale prototype, results showed that the maximum helium leakage rate was well within ITER requirements. As the first hot helium leak test on a large ITER blanket component, the results provide valuable reference data for the further investigation of the acceptance criteria of ITER blanket components. They also provide an important benchmark for developing hot helium leak test standards for the large vacuum components of future tokamaks.
See the gallery of photos below.

Important manufacturing milestone for ITER’s sixth Poloidal Field coil

F4E News - ma, 19/03/2018 - 01:00
F4E and ASIPP half way to completing the winding and impregnation of the superconductors.

Optical properties of tungsten surfaces submitted to fusion reactor conditions

EFDA - wo, 14/03/2018 - 12:00

PhD description:

Thesis advisor:
Laurent Gallais
laurent.gallais AT fresnel DOT fr
+33 (0)6 20 98 69 46
Thesis co-advisor:
Regis Bisson
regis.bisson AT univ-amu DOT fr
+33 (0)4 91 28 83 55

download pdf

This 3 years PhD thesis is offered in the framework of the collaborative project WHeSCI (piim.univ-amu.fr/amidex/whesci), financed by the A*MIDEX foundation (amidex.univ-amu.fr) and proposed in the context of the International Thermonuclear Experimental Reactor (ITER), the international project that aims to demonstrate the technological and scientific feasibility of fusion energy with the Tokamak design (www.iter.org). The WHeSCI project seeks to describe the interactions of the fusion fuel (deuterium and tritium ions) and ashes (helium ions and neutron) with the walls of the exhaust of the reactor (the divertor made of Tungsten, W). The induced material properties modifications are indeed critical for the reactor operation and safety and the successful operation of ITER requires a detailed understanding of the plasma-wall interactions.

In this context, the PhD candidate will be particularly involved in the study of the optical properties of W samples and their evolution with the (near-) surface properties (implanted ions, oxidation, microstructure, roughness…) and applied heat loads (temperature gradients). This work will involve experimental development allowing performing ellipsometric measurement on laser-heated samples from 120 K to > 2000 K in well-controlled conditions (Ultra High Vacuum) and on a variety of W samples, from model (single crystal) to realistic tokamak materials. The experiments analysis will be associated with modelling for the description of ion interactions with W and for the description of the optical properties dependencies with intrinsic material properties and surface state.

The position is based at both the PIIM laboratory and the Institut Fresnel (same campus in Marseille, Provence, France). A highly motivated and experimentally skilled individual is sought, with strong background in physics or chemical physics, knowledge in high vacuum and optics being a plus.

References:
- Minissale M, Pardanaud C, Bisson R and Gallais L, “The temperature dependence of optical properties of tungsten in the visible and near-infrared domains: an experimental and theoretical study” Journal of Physics D: Applied Physics 50, 455601 (2017)
- Hodille EA, Ghiorghiu F, Addab Y, Založnik A, Minissale M, Piazza Z, Martin C, Angot T, Gallais L, Barthe M-F, Becquart CS, Markelj S, Mougenot J, Grisolia C and Bisson R, “Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach”, Nuclear Fusion 57, 076019 (2017)

The post Optical properties of tungsten surfaces submitted to fusion reactor conditions appeared first on EUROfusion.

The lid of the ITER Bioshield is on!

F4E News - wo, 14/03/2018 - 01:00
A spectacular lifting operation delivered by F4E, its contractors, and ITER International Organization.

F4E participates in the first Big Science Business Forum (BSBF2018) alongside Europe’s largest Big Science organisations

F4E Events - di, 06/03/2018 - 01:00
1000 participants from 30 countries gather in Copenhagen from 26-28 February 2018

Europe to lighten 1280 beamlets at the ITER Neutral Beam Test Facility

F4E News - vr, 02/03/2018 - 01:00
SPIDER beam source gets installed in its vacuum vessel.

Exogenous Drivers

EFDA - wo, 28/02/2018 - 15:18

In order to find a balanced setup of the future energy system ETM relies on some exogenous inputs. Next to describing parameters regarding assumed costs and efficiencies for individual technologies, also the development of relevant drivers for the energy demand are considered as input for the model. The following table outlines the relevant drivers:

CODE DESCRIPTION GDP GDP GDPP GDP per capita GDPPHOU GDP per household HOU Number of household PAGR Value Added Agricolture PCHEM Value Added Chemical sector PISNF Value Added Iron and Steel and Non Ferrous metals POEI Value Added Other Energy Intensive industries POI Value Added Other Industries POP Population PSER Value Added Service sector

Klick here to see the assumptions about the develpment of the individual drivers for each single world region in the modell. Individual drivers can be selected/deselected in the legend of the chart.

The post Exogenous Drivers appeared first on EUROfusion.

Out WEST | A purple haze on the screens

ITER - ma, 26/02/2018 - 15:50


Numbers, graphs and a wobbling purple haze on the monitoring screens—this is what a plasma shot looks like when seen from the control room of the WEST tokamak.
Since its first plasma in December 2016, the former Tore Supra tokamak has logged some 2,500 shots. Upgraded, transformed, equipped with an actively cooled tungsten divertor, and graced with a new name—WEST (Tungsten (W) Environment in Steady-State Tokamak)—the machine is being groomed to act as a test bed for ITER, minimizing industrial and financial risks and obtaining experimental data to prepare for operation.
On 16 February, WEST shot the last plasmas of a campaign that had begun one month earlier with the coupling of the machine's two lower hybrid antennas. By the end of this year, the plasma heating system, including three ion cyclotron resonance heating antennas procured by China, should be fully operational.
WEST is now well advanced on the way to becoming an "ITER-like" machine. Out of the 456 actively cooled plasma-facing units in tungsten that make up the divertor, six (three procured by Japan and three by China) are already in place and six more (procured by Europe) will be installed in the coming months. The full actively cooled tungsten divertor configuration should be ready for operation at the end of 2019.
In the meantime, operators in the control room are "learning to drive." Although several features from the "old" Tore Supra have been preserved, WEST is definitely a new machine with a different magnetic configuration (extra coils have been installed under the divertor) that allows for the production of ITER-like D-shaped plasmas.
Over the past few months, the WEST team has been busy fine-tuning the coils, adjusting the position and power of the first lower hybrid antenna, and monitoring the behaviour of the plasma-facing components. Jérôme Bucalossi, who heads the WEST project at CEA's Institut de Recherche sur la Fusion Magnétique (IRFM), is confident that by the time the tungsten divertor is complete, WEST will have reached the high confinement mode ("H mode") that will be ITER's operational regime.
Although almost routine by now (WEST produces an average of 30 pulses per operating day) the pulsating haze on the screens makes a fascinating sight—deuterium nuclei spinning madly for a few seconds inside a magnetic cage. Not quite fusion yet ... but a foretaste in anticipation of the real thing.
Click here to view a video of a plasma shot in WEST.

JT-60SA TF coils have reached their destination

F4E News - ma, 26/02/2018 - 01:00
After an intense and long journey, the JT-60SA Toroidal Field (TF) coils #17 and #20 have reached the JT-60SA Naka site in Japan.

High Performance Computing (HPC) specialist

EFDA - wo, 21/02/2018 - 08:29

The Swiss Plasma Center (SPC) of the Ecole Polytechnique Fédérale de Lausanne (EPFL) is one of the world’s leading fusion research laboratories. Through a wide range of research programs, all connected to education and training at different levels, scientists work to advance the understanding of the plasma dynamics and develop fusion as an energy source. To this end, the SPC theory group makes use of state-of-the-art scientific simulation codes, developed both within the laboratory as well as in the frame of international collaborations, that run on some of the most powerful computers in the world. The SPC is seeking a High Performance Computing (HPC) specialist.

The successful candidate will support the physicists in the SPC’s theory group, in particular carrying out code algorithm adaptation, performance analysis, and code optimisation on various HPC platforms. He/she will also contribute to the group’s publications.

The candidate should hold a degree (Master or possibly PhD) in physics, applied mathematics or computational science and have solid experience in scientific HPC (development, optimisation and porting of state-of-the-art numerical simulation codes) and the ability to carry out projects in a multidisciplinary environment, involving physicists, computer scientists, and applied mathematicians.

Contact:

Prof. Paolo Ricci
paolo.ricci AT epfl DOT ch

Candidates with the appropriate level of experience will be considered for a permanent position. Starting date is to be agreed. For applying, please send a letter of motivation, CV with publication list, and name and email addresses of 3 people willing to write a recommendation letter to Prof. Paolo Ricci (paolo.ricci@epfl.ch)

The post High Performance Computing (HPC) specialist appeared first on EUROfusion.

The last JT-60SA Toroidal Field coils have arrived in Japan

F4E News - di, 20/02/2018 - 01:00
Arriving in style in an Antonov-124, the TF coils have travelled safely from Europe to Japan.

Pagina's