w7x workWhen the new Wendelstein 7-X facility for researching nuclear fusion as a future energy source becomes operational in 2014, it will also incorporate high-precision work and scientific expertise from Poland.

Although scientists from the Max Planck Institute for Plasma Physics (IPP) will play a leading role in the construction of the research facility in Greifswald, quite a few partners will also participate. After the USA, Poland will provide the largest contribution through two cooperative projects. The close of 2012 saw completion of a key six-year project: superconduction technology experts from the Institute of Nuclear Physics of the Polish Academy of Sciences in Cracow connected the 50 superconducting electromagnets – the technical centrepiece of the facility – together in a ring. Around 45 technicians and engineers assembled 121 superconductors up to 14 m long, as well as 240 connectors and 400 supports that had been manufactured at the Forschungszentrum Jülich. When the research facility is operational, current flows through the ring and creates a magnetic cage. This magnetic cage - when hydrogen nuclei are to ignite the fire of fusion and melt into helium nuclei at 100 million degrees Celsius in a future power plant – is prerequisite for containing the plasma to maintain stable, continuous energy production. 

After the departure of the technical staff from Cracow, cooperative efforts will continue with the National Centre for Nuclear Research in Swierk, Poland: The accelerator experts there will take care of production of components for neutral particle heating at Wendelstein 7-X. High-speed particles will be fired into the plasma to help heat it. Manufacturing orders have already been placed with Polish and other European industrial companies. 

Around two-thirds of the costs for both projects are being carried by the Polish Ministry of Science, which made available a total of 6.5 million euros and wants to build its fusion research programme around Wendelstein 7-X. In addition, IPP is funding plasma diagnostics in the form of cooperative projects with universities in Warsaw and Opole. In future, Polish scientists will also carry out research projects directly at Wendelstein 7-X.

Source: Max Planck Institutes

 

EFDA CP12jThe JET shutdown is progressing steadily. Remote Handling Group has been working in-vessel since December. The first task was to conduct a full photographic survey of the inside of the vessel, so that the effects of a year of plasma operations on the ITER-like wall can be assessed. Scientists are now poring over the photographs in detail.

Meanwhile various components have been removed from the torus for closer examination. The tiles in the divertor region (at the bottom of the torus) are fixed to ‘carriers’, and around 20 of these carriers have been removed. They have been transferred to the Beryllium Handling Facility for maintenance of some of the embedded diagnostic systems and removal of a few tiles.

About 600 individual tiles and components have also been removed. Most of these will be replaced without modification, but it was necessary to remove this number in order to gain access to about 50 in particular regions of interest. The 50 will be analysed in laboratories around Europe to look for evidence of erosion and deposition. As many of the tests will be destructive, they will be replaced by brand new tiles as the 600 are re-assembled. Already more than half the tiles taken from the poloidal limiters are back in place.

The next instalment will cover calibration of some diagnostic systems.

 

Source: EFDA

CERNCPITERENGINEERINGNET.EU – The engineering company Air Liquide has secured two contracts to build extreme cryogenic systems for the ITER and the related JT-60SA research projects on fusion. The total value of these equipment sales contracts will reach over €100million.

Based near Marseille, in France, the ITER project plans the creation of an experimental reactor intended to illustrate the scientific and technical feasibility of fusion. This process generates little waste and eliminates any risk of reactor runaway. 

To obtain the very powerful electromagnetic fields necessary to confine fusion, superconducting magnets must be used, which only work at extremely low temperatures.

For this project, Air Liquide will provide the biggest centralized refrigeration system ever built. This cryogenic equipment is essential for maintaining an extremely cold temperature for the 10,000 tonnes of superconducting magnets used on the Tokamak. 

This sophisticated scientific instrument confines the plasma that makes it possible to achieve the conditions necessary for controlled fusion. The closed circuit refrigeration system is based on the properties of liquefied helium, whose temperature is close to the lowest possible temperature 0 K, or -273°C, called "absolute zero". 

Between the end of 2015 and the beginning of 2017, Air Liquide will install three refrigerators for a global cooling capacity of 75 kW at 4.5 K, or - 269 °C.

The purpose of another project, JT-60SA, is to support the ITER project's research activities by working on the capacity to control and maintain the plasma for several hours. 

JT-60SA, based in Japan, is designed to optimize plasma configurations for the ITER project. It is led by the Japanese Atomic Energy Agency in collaboration with the French organisation CEA. For this project, Air Liquide will commission, in 2015, a helium refrigeration system, intended to cool the Tokamak.

François Darchis, Senior Vice-President: "After the CERN's LHC and Kstar in Korea, these projects once again prove our capacity to meet major scientific challenges by supplying very high tech systems." << (BB) (photo: Air Liquide, cryogenic system at CERN)

 

Source: engineeringnet.eu

k-demoHarnessing fusion energy in the 21st century is a lot like going to the Moon in the 1970s. At that time, as each manned flight project unfolded, another one was already in the plans. One half-century ago, the Mercury, Gemini and Apollo programs were the space equivalent of the fusion projects JET, ITER and DEMO.
 
In space exploration, as in fusion research, planning for the next step when the present one has just gotten underway is a necessity. This was the case with JET, which began operating two years before the ITER project was officially launched (1983), and it is happening now with ITER, with planning for the next stage device underway even before fusion experiments have started in 2027.
 
Hundreds of physicists and engineers throughout the world are now planning for DEMO, the generic name for a pre-industrial demonstration power plant that will bring all technologies to the level of performance, reliability and efficiency required for the production of electricity.
 
As was demonstrated during the recent international workshop held at the University of California, Los Angeles, on 15-19 October 2012, the time is now ripe for developing these ideas.
 
Korea (Pop. 49 million), which relies on imports for more than 90 percent of its energy needs, is among the countries that have embarked on the development of a preliminary concept for DEMO. The main parametres of the Korean DEMO ("K-DEMO") have already been defined and construction is expected to be completed in 2037.
 
Newsline sat with Kijung Jung, head of the Korean ITER Domestic Agency, to learn more.
 
Newsline: Many countries and groups are currently working on a concept definition for DEMO. Would you say that Korea has now taken a decisive step in DEMO's direction?
Kijung Jung: I would say that the decisive step was taken more than five years ago, when the Fusion Energy Development Promotion Law (FEDPL) was enacted. Korea was the first country in the world to lay a legal foundation for fusion energy development. It is within this framework that our government launched DEMO R&D planning project at the end of 2012 and we are expecting results at the end of June 2013. A preliminary validity review process and a main project validity review process will take place at the end of that year. We hope the actual R&D program will be launched in 2014-2015.
 
The recent workshop at UCLA made one thing very clear: there are about as many different potential DEMOs as there are countries involved. Does Korea already have an idea of what K-DEMO could be like?
 
Three options are being considered at this stage—machines with a respective major radius of 6.0 m, 6.65 m and 7.15 m. But the tokamak with 6.65 m major radius has become the main target for detailed study. The peak toroidal field is ~16 Tesla and the toroidal field at plasma centre is ~7.6 Tesla.
 
How will Korea's decision impact its participation in the ITER project?
 
It will not. Korea will of course remain a strong partner in the ITER project as it has been for the past ten years. Most of the engineering results from ITER project will be incorporated into our K-DEMO and Test Blanket Module activity will be accelerated as a part of DEMO breeding blanket R&D.
 
According to media reports K-DEMO could be completed in the 2030s. Considering that ITER will begin deuterium-tritium operations in 2027 and that results from the ITER experiments have always been defined as necessary to the design of a DEMO, how do you reconcile the two project schedules?
 
The target completion date for K-DEMO is set at the end of 2037. Because there may not be enough nuclear data by that time, K-DEMO will also be used as a component test facility during its first operational phase, which will extend from 2037 to approximately 2050. During the second operational phase, which is planned to start in 2050, most in-vessel components will be replaced for full steady-state operation and electricity generation.
 
How will K-DEMO approach the plasma-facing materials issue?
 
The main issues for K-DEMO development are the divertor and the blanket issues. We will try to resolve these to the extent possible in collaboration with ITER Members. However, the issues will be finally resolved during the second K-DEMO operation stage.
 
Can you provide an estimate of K-DEMO's construction cost? How does it compare to the ~ EUR 13 billion ITER price tag?
 
At present, it is premature to estimate K-DEMOs cost.
 
 
Source: EFDA

compassA five year quest has borne fruit with the COMPASS tokamak in Prague’s Institute of Plasma Physics (IPP) achieving H-mode performance. The milestone marks a new era for fusion research in the Czech Republic, which began in 2007 when the COMPASS tokamak was transferred from the CCFE in UK.

“We have historical links which made us a regional centre for scientists from Hungary, Bulgaria and Poland, but now scientists from West Europe have also been visiting COMPASS – it’s another meeting point for the fusion community.” says fusion scientist Dr Jan Mlynář from IPP.

“It is very important that we can now do H-mode operation as this is the standard ITER scenario. We have invested lots of money into making an “ITER-like” operation scenario, in particular we purchased new heating neutral beams to achieve relevant ion temperatures and thus hopefully create Type I ELMs.”

Now the ITER-like mode of operation has been established, COMPASS can be used as a small scale test bed for ITER performance: combining COMPASS’s results with similar tests in ASDEX Upgrade (three times larger) and JET (six times larger) gives excellent extrapolation to ITER (ten times larger).

However, for some studies the overall size does not matter, and in these areas COMPASS really comes into its own. H-mode’s high confinement stems from a sharp increase in the pressure at the edge of the plasma, known as the edge transport barrier or pedestal; COMPASS’s ability to reproduce H-mode makes it arguably as useful a device as the bigger machines in studying this plasma edge phenomenon, says Dr Mlynář.

“We can now measure and detail properties of this pedestal. All machines that have H-mode have this edge pedestal, however nobody really understands the details of physics behind this pedestal… Our advantage is that we are not so expensive and so “heavy” in operation. It is simpler to test different ideas or different new hardware.”

“Also, big machines are usually overbooked – scientists need a really good reference to get research time at ASDEX or JET, and promising results from smaller tokamaks is a very good reference.”

With the result in Prague coinciding with the recent release of EFDA’s road map to fusion, it’s clear that COMPASS will have a significant part to play in the navigation towards the goal of fusion energy!

The Institute of Plasma Physics is the Czech Republic’s signatory to the European Fusion Development Agreement.

 

Source: EFDA

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Research projects carried out at the IPPLM are funded by the Polish Ministry of Education and Science, the National Science Centre and by the European Commission within the framework of EUROfusion Consortium under grant agreement No 101052200. Financial support comes also from the International Atomic Energy Agency, European Space Agency and LaserLab Consortium as well as from the Fusion for Energy Agency.

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